ML20211J452

Forwards Selected design-related 10CFR50.55(e) Items.Related Deficiency Repts Also Encl.Related Correspondence

ML20211J452
Person / Time
Site:	Comanche Peak
Issue date:	11/04/1986
From:	Ellis J Citizens Association for Sound Energy
To:	Bloch P Atomic Safety and Licensing Board Panel
References
CON-#486-1420 OL, NUDOCS 8611110137
Download: ML20211J452 (131)

Text

," .

WTED CORRESPONDQ4SA C A S E (CITIZENS ASSN. FOR SOUND ENERGY)

214/9M-94M DOLKETED eUmc November 4, 1986 '85 NOV -7 P1 :25 Administrative Judge Peter B. Bloch Dr. Walter H. Jordan

" 9 U. S. Nuclear Regulatory Commission 881 W. Outer Dr % 'E r -

Atomic Safety and Licensing Board Oak Ridge, Tenndskk3]830 Washington, D. C. 20555 Dr. Kenneth A. McCollom 1107 West Knapp Street Stillwater, Oklahoma 74074

Subject:

In the Matter of Texas Utilities Electric Company, g g.

Request for an Operating License for Comanche Peak Steam Electric Station, Units 1 and 2 Docket Nos. 50-445 and 50-446 O Design-Related Pot'ential 10 CFR 50.55(e) Items In accordance with the Board's desires to be kept up-to-date on matters of potential significance, CASE is attaching copies of selected potential 50.55(e) notifications for the Board's review.

We realize that the Board has been provided in Applicants' Progress Reports with listings of recent potential 10 CFR 50.55(e) items which have been reported by Applicants.to NRC Region IV as required by NRC regulations.

However, the listings do not give much detail as to what the concerns are.

In reviewing the quantity and type of potential 50.55(e) items received

.recently, we have come to the conclusion that it might be helpful to the Board to have copies of the actual notifications, which give significantly more details than are indicated by the listings alone.

It should be noted that these are only for about the past year or so; further, they are only selected notifications which either definitely are related to design or which appear to have some design implications (i.e., we have not included those which are strictly construction-related). These are not necessarily even all of the design-related potential 50.55(e)'s/SDAR's (Significant Deficiency Analysis Reports), but we believe should be sufficient to give the Board a better understanding of the number and magnitude of the problems being identified regarding design / design OA.

R spectfully submitted, r

4 Juanita Ellis, President cc: Service List 8611110137 861104 1 PDR ADOCK 05000445 G PDR h

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ATTACMENT TO CASE'S 11/4/86 LETTER TO LICENSING BOARD ATTACHING POTENTIAL 10 CFR 50.55(e) SDAR'S (SIGNIFICANT-DEFICIENCY ANALYSIS REPORTS)

NOTE: Items attached are marked with in front of SDAR number.

SDAR INDEX-09/22/86 NLQ. SUBJECT DETERM. STATUS 84-01 CABLE TRAY SUPPORT COLLMN(CABLE SPREAD ROOM) NR TXX-4154 84 -02 DIESEL GENERATORS DEFECTIVE PUSH RODS R TXX-4108 84-03 INSTRUMENT TUBING NR TXX-4110 84-04 FERRORESONANT TRANSFORMERS R TXX-4109 84-05 PROTECTIVE COATINGS ADHESION TESTER NR TXX-4248 84-CS PIPE SUPPORT DESIGN ERROR NR TXX-4107 84-07 DEFICIENT LUG CRIMPING R TXX-4135 84-08 THERMAL EXPANSION OF CURTAIN FIRE DAMPERS .R TXX-4257 84-09. THRUST BEARING LUBRICATION NR TXX-4227 84-A INSPECTOR EYE EXAMINATION RECORDS NR TXX-4204 84-10 RODENT DAMAGE TO CLASS 1E CABLES NR TXX-4175 84-11 UNAUTHORIZED THERMOLAG. INSULATION NR TXX-4178 84-12 IMPACT OF HELB TEMPERATURES ON QUALIFIED EQUIPMENT.OUTSIDE CONTAINMENT P* 10/24/86 84-13 FSAR AND TECHNICAL SPECIFICATION CONSISTENCY NR TXX-4213 84-14 ROCKBESTOS CABLE DEFICIENCY NR TXX-4214 84-15 IhDETERMIN. FLORIDE CONTENT-MANVILLE INSULATION NR TXX-4221 84-16 QUALIFICATION OF MAIN STEAM RELIEF VALVES NR TXX-4330 84-17 FLOODING CONCERNS R TXX-4263 84-18 UNQUALIFIED LIMITORQUE ELECTRIC MOTORS NR TXX-4308 84-19 DG MATERIAL DEFECT (VALVE SPRINGS) NR TXX-4270 84-20 DG MATERIAL DEFECT (DELIVERY VALVE HOLDER) NR TXX-4309 84-21 UT REQUIREMENTS: CLASS 1 PIPING NR TXX-4292 84-22 .CCW SYSTEM DESIGN CONCERN NR TXX-4351 84-23 CONAX PENETRATION CONNECTORS NR TXX-4375 84-24 PREOPERATIONAL TESTING ACTIVITIES NR TXX-4372' 84-25 AIR-OPERATED DIAPHRAGM VALVES NR TXX-4318 84-26 NSSS AUXILIARY RELAY RACKS . NR TXX-4317 84-27 VENTILATION EXHAUST DAMPERS R TXX-4409 84-28 ROSEMOUNT TRANSMITTERS LEAKAGE R TXX-4364 84-29 SAFE SHUTDOWN CAPABILITY FOR FIRE-C.R. HVAC R TXX-4350 84-30 SAFETY CLASS DESIGNATION OF INSTRUMENTS LINES NR TXX-4362 84-31 CONTROL ROOM SEPARATION WALL R TXX-4349 84-32 CIASS lE BARTON PRESSURE SWITCHES-PART 21 NR TXX-4363 84-33 RELAYS OUTSIDE SPECIFICATION NR TXX-4376 84-34 UNIT 2 STRUCTURAL EMBED WELDING NR TXX44,433 1984: 35 TOTAL SDARS-9 REPORTABLE.1 POTENTIAL

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ETR: INTEM-07/01/25

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g5-ci MAIN CCh... .ae.D CAI* I SIPAP A!!ON VIO LA!!!N  !TR TXX-44-, l g5-C2 CAELI SPPIAD ROOM IIRI PROTECTION-3 HE EAP0.!IR !G TXX-44'., )

85-03 STIAM GENERATOR UPPER LA~ IRA

• SUP.: ORT EIAMS R TXX-4415 i 35-04 CON AINMINT SPRAY EIACIR ISCLAT!ON VALTIS R TXX-44--

25-05 OG INGINI CONTROL PANIL AIR FILTIR SCWLS R TXX-44 3 85-06 IRT COMP

• IR IRMINATION POINTS NR TXX-4447 ,

25-07 ILI TRICAL CA5LI EU*T SPLICIS !G TXX-4430 85-03 SUMP' ISOLATION VALVI MCTORS NR TXX-4431 25-09 VALVI WIIGH~ O!SC FANCIIS , !G TXX-4473 25 KILIANCE _ CONTROL BOARD IQ DOCUMENTATION NR TXX-4523 25-11 INSTRUMENTATION TUEI T:~~ING LCCATIONS R TXX-4454 85-12 ATW PRISSURI CONTROL-TIID WATIR LOW TLOW TO S/G R TXX-4456 85-13 UNDITIC*ID TAILURE IN SATITY TIATURIS ACT.SYS. R TXX-4457 25-14 UNAUTHORIIID SUPPORT RIPAIRS R TXX-4465 85-15 IQUIPMENT HATCH UNIT 1 UNIVAL. EEARING TORCIS NR TXX-4460 85-16 PHOINIX STIIL-PART 21 WALL TMICXNISS QUISTION NR TXX-4505 85-17 PART 21-CORI IXIT *MPERATURI MONITORING IRRORS NR TXX-4485 85-18 SPECITIC CRITERIA TOR CONCRITI ANCHORS IN THE.

PROXIMITY OF .W-.EIDDID ANGLID NOT DITINID R TXX-4492 85-19 CONDUIT SUPPORT SPANS P* 10/21/86 85-20 WHIP INTERACTION POSSIBLI-TW BREAK /CS HEADIRS R TXX-4516 85-21 DG POTINTIAL CONTROL PANIL OVERMIATING NR TXX-4493 I 85-22 CONTAINMINT ISOLATION VALVIS NR TXX-4575 85-23 CONTAINMENT SPRAY PUMP NR TXX-4563 85-24 TIPEINATION OF TIRI DITICTION DITICTORS NR TXX-4533 85-25 SIQUINCING TIRE PROT. COMPONINTS FOR HVAC/CCW NR TXX-4578 26 UPPER LATERAL RISTRAINT EMBIDMINT DESIGN P* 08/15/86 85-27 SIISMIC GAP m 3 THAN DESIGN-CPRT ITIM II.C R TXX-4650 85-28 PIPI SUPPORTS WILD LINGTH ANALYSIS NR -TXX-4550 85-29 DESIGN OF ARCHITICTURAL TIATURIS R TXX-4552 ,

85-30 SWITNGIAR CABINIT VINDOR TIRMINATION NR TXX-4598 31 ILICTRICAL RACIWAY SUPPORT SYSTIM DISIGN P* 10/21/86 85-32 TIIDWATER RIG VALVI SINGLI POWER SUPPLY NR TXX-4600

- 85-33 NON-SIISMIC TO SIISMIC INTERACTION NR TXX-4577

- 85-34 CONDUIT SUPPORT SYSTEM -

P* 10/21/86

- 85-35 CABLI TRAY. HANGER DISIGN P* 10/21/86

- 85-36 TRAIN 'C' CONDUIT SUPPORTS Pe 07/03/86 ,

85-37 QUALITICATION/CIRTITICATION OF INSPECTORS R TXX-4569 85-38 CONTROL BOARD SIPARATION MATIRIAL NR TXX-4715 l

85-39 ICUIPMINT CONDUIT INTERTACI P* 08/15/86 40 TLUX MAPPING SEAL TABLE RISTRAINTS R TXX-4633 41 COMPUTER PROGRAM IRRORS !G TXX-4716 85-42 CONDUIT LOADING BY TMIRMOLAG P* 10/21/86 43 QUALITICATION OF PIRIT TIMPIRATURIS R TXX-4659 25-44 QUALITICATION OT 480V SWITCHGIAR

• P* 07/17/86 25-45 RIBAR DAMAGE . NR TXX-4761 85-46 DAMAGI STUDY IVAL. OF W ANALYIID PIPING R- TXX-4658 85-47 USE OF AMPTITIOR IIA RILAYS !G TXX-4682 85-48 DG INTATI S!LINCIR INTIRNALS  !TR TXX-4683

--- 8 5 -4 9 MAIN STIAM LINI TLUID TRANSIINT R TXX-4656 50 CABLI TRAY TII T!""!INGS P* 10/21/86 25-51 APPLICATION OT LOW SULPHUR CONTENT A588 STIIL !iR TXX-47:2

_ 85-52 CABLE TRAY HANGIR RT*,*IRITICATION PROGRAM R TXX-4657

-- 85-53 ADICUACY 07 SIISMIC CATIOGRY :: PLATTORMS P* 07/30/86

~ 25-54 SI:3M:0 CUA* T: CAT GN OT h 'AC SUPPORTS P= 09/26/86

- evene-s n e r *m icos. 54 ---se ensue _ en-ry r t

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SDAR INDEX-09/22/86 3 SI*BJECT DETERM. STATUS 86-01 WEIDMULLER TERMINAL BLOCKS NR TXX-4712 86-02 TURBINE-DRIVEN AFW PLNP PERFORMANCE NR TXX-4723 86-03 CLASS lE INSTRUMENT TECHNIQUES R TXX-4692

,86-04 RICHMOND INSERTS TO EMBEDDED PLATE P* 10/20/86

_ 86-05 SAFETY CLASS PIPE SUPPORTS MOUNTED TO NSS EMBEDDED PLATE NR TXX-4776 86-r6 PUMP AND DRIVER DOWELING NR TXX-4704

,86-07 SERVICE WATER SYSTEM LEAKAGE R* 01/30/87 86-08 SUPER HILTI-KWIK BOLT INSTALLATIONS P* 12/01/86 86-C3 DG INLET / EXHAUST VALVE SP3INGS NR TXX-4724 86-10 ELECTRICAL PENETRATION ASSEMBLIES R* 09/26/86 86-11 ' PLNP IMPELLER LINEAR INDICATIONS R* 09/23/86 86-12 C0FNODITY INSTALLATIONS AT SEC. WALL DESIGN GAP P*

86-13 11/24/86 JET IMPINGEMENT LOAD REVIEW P* 10/21/86 86-14 6.9KV SWITCHGEAR BREAKER WELD FAILURE P* 10/21/86 86-15 DIESEL GENERATOR CONTROLS P* 09/30/86 16 FIRE EFFECTS ON INSTRUMENT TUBING P* 10/22/86 86-17 MINIMLN CONCRETE COVERAGE P* 11/24/86 86-18 SAFETY CHILLED WATER CHILLER UNITS R* 12/17/86 86-19 PRESSURE INSTRUMENT INSTALLATIONS R* 09/26/06 86-20 WFI NUCLEAR PRODUCTS NR TXX-4870 86-21 QUALIFICATION OF RAYCHEM KIT NPKS-02-01 P* 09/26/86 22 SG'S AREA FAN COOLERS P* 12/12/86 86-23 P-10 PERMISSIVE R TXX-4835 86-24 SPACE AND MOTOR HEATERS P* 11/14/86-86-25 BREAKER / FUSE COORDINATION NR TXX-4964 86-26 CONTAINMENT SPRAY SYSTEM PIPING NR TXX-4799 86-27 CCW RADIATION DETECTORS NR TXX-4800 86-28 SERVICE WATER SYSTEM DISCHARGE NR TXX-4801 86-29 ACCEPTANCE TEST OF AIR OPERATED VALVES NR TXX-4802 86-30 UPS INVERTERS NR TXX-4965 86-31 DG LUBE OIL SUMP TANK _ FOOT VALVES R* 11/26/86 86-22 THRU-WALL EBMEDDED CONDUIT SLEEVES P* 11/21/86 86-33 STIFFNESS VALUES FOR CLASS 1 STRESS ANALYSIS P* 10/17/86 86-34 DEFECTIVE FIRE STOP INSTALLATIONS NR TXX-4966 25 MOTOR OPERATORS FOR MANUAL VALVES R* 05/15/87 86-26 PIPE SUPPORTS R* 09/26/86 l 86-37

• CLASS lE. BATTERY CHARGER COMPONENTS P* 10/15/86 L 86-38 TRACEABILITY OF lE PIGTAIL EXTENSIONS P* 12/17/86 39 CABLE TRAY "C-TYPE" CLAMP SHIM DIMENSIONS P* 10/21/86 86-40 APPLICATION OF NON-QUALIFIED AGASTAT RELAYS P* 10/10/86 41 SMALL LOCA MODE 4 OPERATION P* 10/29/86 42 I&C CABINET POWER SUPPLY BREAKERS NR TXX-4993 86-43 ITT BARTON MODEL 580 SERIES SWITCHES P* 09/26/86

,86-44 WELDED ATTACHMENTS TO EMBEDDED STRIP PLATES P* 10/20/86 86-45 SEISMIC CATEGORY II SYSTEMS & COMPONENTS P* 10/03/86

_ 86-46 GOULD BATTERY RACKS TRANSVERSE BRACING P* 10/21/86

,86-47 FIRE PENETRATION SEAL DESIGN NR TXX-4996 86-48 ADEQUACY OF NONCONFORMANCE DISPOSITIONS P* 10/24/86 86-49 CONAX ADAPTOR MODULES & ELECTRICAL PENETRATIONS P* 10/10/86 86-50 UNISTRUT SPRING NUTS ON INSTRUMENT SUPPORTS P* 10/10/86 86-51 ANCHOR BOLTS SUPPLIED BY HILTI P* 11/14/86 86-E2 CABLE TRAY SPLICES / CONNECTIONS P* 10/21/86 86-03 SEISMIC DESIGN OF CONDUIT P* 10/21/86 86-54 ORIGINAL DESIGN OF CONTROL ROOM CEILING P* 10/03/tm 86-55 SEISMIC AIR GAP DESIGN ADEQUACY P* 11/21/86 86-E6 DG ENGINE CONNECTING ROD ASSEMBLY NR TXX-5025

86-C7 REINFORCING STEEL IN UNIT 1 RX CAVITY WALL P* 09/29/86 86-58 DRILLING / CUTTING OF REINFOR. STEEL IN FUEL BLDG P* 09/29/86 86-59 SUPPOET INSTALLATIONS-SPACING VIOLATIONS P* 09/29/86 1

L

--. - _ - - . ~ . .

SDAR INDEX-09/02/86 3 SUBJECT DETERM. STATUS

, 86-60 POLAR CRANE GIRDER AND GIRDER SUPPORT SHIM GAPS P* 10/03/86 86-61 POLAR CRANE RESTRAINTS P* 10/03/86 86-62 POLAR CRANE SUPPORT STRUCTURE P* 10/03/86-86-63 BROKEN COTTER PIN ON SNUBBER P* 10/03/86 S6-64 COATINGS FOR DIESEL FLTL OIL TA.MCS Pt 10/03/86 86-65 UNCONSOLIDATED CONCRETE-UNIT 2 RCB EXT. WALL P* 10/15/86 1986: 65 TOTAL SDARS--10 REPORTABLE, 39 POTENTIAL

• Future report due to f1RC

. - 86-67 Pre-Operational Vibrational Test Criteria' -

_ 86-70 Elevated Temperature Effects on Instrument Supports and Tubing

, 86-72 Small Bore Fiping and Supports l

1 w - -. .m ,. _ _ _ _ - - _ . . _ _ - - _ . - - ~ _ -c, -.__--- - -.----.,.--_s.--- -- , _ _ - , _ _ - - - - - - ,_y,-

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Log 0 TXX-6045 File 0 10110 903.11 TEXAS UTILITIES GENERATING COMPANY mEYWAY TOWBE . ese NOSTBE 012VE ST1REET. L.B. S 8

• Dh, TEXAS 78901 October 21, 1986 4

73%7AM."n'.h Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 IMPACT OF HELB TEMPERATURES ON QUALIFIED EQUIPMENT OUTSIDE CONTAINMENT SDAR: CP-84-12 (INTERIM REPORT)

Dear Mr. Johnson:

On June 4,1984, we verbally notified your Mr. D. Hunnicutt of a deficiency involving the environmental qualification of equipment outside containment for high energy line breaks (HELB). This is an interim report of a potentially reportable item under. provisions of 10CFR50.55(e). Our most recent interim report was logged TXX-5029, dated September 19, 1986.

The remaining qualification issue yet to be resolved is a comparison of the cable temperatures in the area of concern to the existing established qualified temperatures. After identifying cable types and locations, a.

thermal transient analysis will be performed to determine the temperatures to which the outer cable layer is exposed. These temperatures will be used to determine if the ambient temperature will exceed the cables' qualified environmental temperature.

Current project scheduling indicates our evaluation will be completed by December 1, 1986.

A DEVISION OF TEXAS (ff7IJTTES EIECTEfC COMPANY

' ~

TXX-6045 October 21, 1986 Page 2-We are continuing our evaluation of this issue and anticipate submitting our next report by December 19, 1986.

Very truly yours, rk/1 W. G. Cou sil By: . , . .

8 G. 1. Keeley ~ /

Manager, Nuclea_rs L sing JCH/gj c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

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Log # TXX-5029 File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTH OLIVE STREET. L.B. el . DAI LAs. TEXA8 75303 September 19, 1986 fiM0i* .f.7.TA Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 IMPACT OF HELB TEMPERATURES ON QUALIFIED EQUIPMENT OUTSIDE CONTAINMENT SDAR: CP-84-12 (INTERIM REPORT) ,

Dear Mr. Johnson:

On June 4,1984, we verbally notified your Mr. D. Hunnicutt of a deficiency involving the environmental qualification of equipment outside containment for high energy line breaks (HELB). This is an interim report of a potentially reportable item under provisions of 10CFR50.55(e). Our most recent interim report was logged TXX-4912, dated July 16, 1986.

The course of our evaluation has included the plant specific application of the unreviewed safety question investigated by the Westinghouse Owners Group involving the thermal analysis of the environment, and the effects of superheated steam on the operability and qualification of Class 1E components.

Currently, these efforts have been completed with the exception of an analysis to determine the cable sheath temperature inside conduits in the break compartments during the line break scenario. A schedule for completion of this analysis is expected October 3, 1986.

We are continuing our evaluation of this issue and anticipate submitting nur next report by October 24, 1986.

Very truly yours, W. G. Co il 7 By: '

G. S. Keelst /-

Manager, Lice ng JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcements (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Log # TXX-6046

.- 4 File # 10110 l

903.11 TEXAS UTILITIES GENERATING COMPANY u v..,io . ,=.uv. a. . ..*u . ,

October 21, 1986

,1%7&f?.fA*.i Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan P1aza Drive,-Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE' PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 CONDUIT SUPPORT SPANS SDAR: CP-85-19 (INTERIM REPORT)

Dear Mr. Johnson:

On May 15, 1985, we verbally notified your Mr. D. Hunnicutt of a deficiency regarding the use of a nonrepresentative sample in determining generic values for typical conduit span calculations. Our most recent interim report was logged TXX-4804, dated May 16, 1986. We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.

DESCRIPTION The seismic conduits and conduit supports at CPSES are segregated into Trains A, B and C. Conduit supports on Trains A and B are safety related. Train C conduit supports are considered to be non-safety related with the following exceptions:

- Unit 2, Train C conduits which are larger than 2 inches in diameter and their conduit supports are seismically designed with the same requirements as Trains A and B.

- Unit 1, supports on Train C conduits which are over 2 inches in diameter are grouped into three categories: 1) seismically designed, 2) seismically restrained with aircraft cables, and 3) non-seismically designed. This issue addresses the conduits which are seismically supported or restrained.

Seismic conduit and support design is governed by two documents: the S-0910 design package for Unit I and Common areas, and the S2-0910 design package for Unit 2. These documents describe various types of " engineered" and " generic" supports along with the allowable conduit spans. Supports deviating from generic support criteria are ' identified as either " Modified" or " Individually Engineered".(IN) supports.

External Design Reviews identified a specific concern questioning the yield stress tests used to justify the conduit span calculations for Units 1 and 2.

This issue is addressed as CPRT Program Plan Item DSAP VIII. A comprehensive reverification plan has been implemented in order to resolve these concerns.

4 mmenw orrazam ummes snacmc cone 4nr

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TXX-6046 October 21, 1986 l Page 2 of 2 )

Results of this verification to date indicate that a number of supports in Unit I have reduced capacities for certain elevations and buildings.

Moreover, certain extreme span configurations may cause overstressing of the conduit and overloading of supports. Evaluations of conduit support spans in Unit 2 are in progress.

SAFETY IMPLICATIONS Failure of seismic category conduits and conduit supports to meet the design criteria could result in an inability of associated safety related systems to perform as required for safe operation and shutdown.

i CORRECTIVE ACTION For Unit 1, field verifications and subsequent engineering evaluations are.

continuing. Formulation of corrective actions resulting from this evaluation will be complete by February 17, 1987.

For Unit 2, a complete design verification of the S2-2910 design package is being conducted. This design verification and tha preparation and verification of the isometric drawing packages is contingent upon Project schedules which are currently being redefined.

We anticipate submitting our next report by March 10, 1987.

Very truly yours,

, j j G.~S. Keele b 6 Manager, Nuclear icensing i

JCH/gj c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcements (15 copies)

U. S. Nuclear Regulatory Commissioa

, Washington, D.C. 20555 1

l l

l l l

l

Log # TXX-4702 File # 10110 903.9 TEXAS L'TILITIES GENERATING COMPANY SKYW AY Towru . 400 NORTH OLIVE STREET. LB. 3 3 . DALLAS. TEXAss TS201 '

February 12, 1986

.*n% ANY,?.*,k Mr. Eric H. Jonnson, Acting Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 75012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 CONDUIT SUPPORT SPANS SDAR: CP-85-19

Dear Mr. Johnson:

On May 15, 1985, we verbally notified your Mr.'D. Hunnicutt of a deficiency regarding the use of a nonrepresentative sample in determining generic values for typical conduit span calculations. This is an interim report of a potentially reportable item unoer the provisions of 10CFR50.55(e). We have submitted interim reports logged TXX-4489~and TXX-4597, dated June 11, 1985, and October 16, 1985, respectively. This issue is related to CP-85-34 Conduit Support Design, which is being evaluated under CPRT Program Plan Item VIII and scheduled for resolution by April 25, 1986.

We are continuing our evaluation and anticipate completion of our final report by May 16, 1986.

Very trulg,yours, ,,

W. G. Counsil JCH/ arm c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies).

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIYL%IO.% LW TCXAN t*TILITIE.% El.CCTRIC CU%tPANY

-+ - - _ . . - - . - - . _ . . . = . . . - . .-_

Log # TXX-6063 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY

1. SKYWAY TOWER . 435 NOST,8 OLIVE STREET. LB. St . DA11AS. TEXAS 78MB October 27, 1986 5'##5hf..U E Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects >

U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX . 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 UPPER LATERAL RESTRAINT EMBEDMENT DESIGN SDAR: CP-85-26 (INTERIM REPORT)

Dear Mr. Johnson:

On July 19, 1985, we verbally notified your Mr. D. Powell of a deficiency

.regarding the Unit I steam generator upper lateral restraint embedment design.

This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our last interim report was logged TXX-4961 dated August 18, 1986.

The scope of this issue has been expanded in order to analyze the steam generator upper lateral restraint embedments based on revised loadings on the beams and their connections. These revised loadings are a result of a design bounding assumption that the Steam Generator compartment platforms are considered removed. Prior designs were based upon attenuation of pressure loadings in the upper compartment regions due to the restricting effects of compartment platforms located in the vent paths.

j We anticipate submitting our next report on this issue no later than December 3, 1986.

Very truly yours,

W. G. Counsil l BSD/amb .

c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission j Washington, D.C. 20555 3

e A OfFIsf0N OF TEXAS LTILITIES 512CTR8C CUMPANY J

. _ . , . - . _ = . _ , ~ _ . , - . - - _ - . _ _ - , . _ , . . _ , _ _ , , _ _ _ , . _ . _ - _ __ _ , . _ . . _ . , _ _ _ . . _ - . _ _ _ _ , _ , . __ _ _ _ _ _ _

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Log # TXX-4961 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NORTis OtJVE STREET. L.88 SI . DALLAS. TEXAS 78201 August 18, 1986

.T2WL%?A?.7.'.h Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. tiuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 UPPER LATERAL RESTRAINT EMBEDMENT DESIGN SDAR: CP-85-26 (INTERIM REPORT)

Dear Mr. Johnson:

On July 19, 1985, we verbally notified your Mr. D. Powell of a deficiency regarding the Unit I steam generator upper lateral restraint embedment design.

This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our last interim report was logged TXX-4877, dated June 27, 1986. On August 15, 1986, we requested and received an extension until August 18,'1986, in submitting this report from your Mr. D.

Hunnicutt.

Our evaluation of this issue has been expanded to address the comments of the third-party review organization (TERA) and Stone and Webster Engineering (SWEC). We anticipate submitting our next report by November 3, 1986.

Very truly yours,

//Y W. G. Counsil By: M G. 5. Keeley N//

Manager, Nuc h /4 W ng JCH/arh /-

c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 a inviswu or rrxas turries tercrme ca.straxr

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File # 1011@

903.8 N . . - -

. TEXAS UTILITIES GENERATING COMPANY anyw Av vowns . 4ao woorn ouva arrazer. t m. e &

• DAIAAS. TEXAB 78308

June 27, 1986

• .0%"SMP.7.',$ ,

' Mr. Eric H. Johnson,. Director Division of Reactor Safety and Projects U. S. Nuclear Regulatorystomnission s,' 611 Ryan Plaza Drive', Suite 2000

- s . Arlington, TX 76012 s

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET fio. 50-445 UP?iR LATERAL RESTRAINT EMBEDMENT DESIGN

- SDAR: CP-85-26 (INTERIM REPORT)

Dear Mr.' Johnson:

i On July 19, 1985, we verbally notified your Mr. D. Powell of a deficiency regarding the Unit 1 steam gererator upper lateral restraint embedment design.

This is_ an interim report of .a potentially reportable item under the provi-sions of'10CFR50.55(e). We hse submitted interim reports logged TXX-4532, TXX-4626, TXX-4671, and TXX-4822, dated August 9, 1985, November 20,.1985, January 22, 1986, and May 23,-1986, respectively.

The concern is being evaluated under the CPRT Program Plan Item V.b. We anticipate submitting our next report by August 15, 1986.

N Very truly yours, t' ,

W. G. Counsil JCH/arh

, c - NRC Region IV'(0 + 1 Copy) l Director, Inspection & . Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington,.D.C. 20555

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A DIV1580N Of TCxAs t*TIllTTES ELCCTRic ContPA.%T t

Log # TXX-4671 TEXAS UTILITIES GENERATING COMPA.W Fi1e # 10110 SKYW AY TOWER . 400 NoaTH O.JYE ETBEET. L.B. e B

• 1)AL1.A6. TEXAa 73203 January 22, 1986

.7.7%70.*E".7.".5 Mr. Eric H. Johnson, Acting Director Division of Reactor Safety and Projects U.S. huclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION i DOCKET NO. 50-445 1 UPPER LATERAL RESTRAINT EMBEDMENT DESIGN SDAR: CP-85-26

Dear Mr. Johnson:

On July 19, 1985, we vernally notified your Mr. D. Powell of a deficiency regarding the Unit I steam generator upper lateral restraint embeament design. This is an interim report of a potentially reportable item unaer the provisions of 10CFR50.55(e). We have submitted interim reports TXX-4532 and TXX-4626, dated August 9, 1935, and Novemoer 20, 1985, respec-tively. This concern is being evaluated under CPRT Program Plan Item V.b and is scheduled for resolution by May 2, 1986.

We are continuing our evaluation and anticipate completion of our final report by May 23, 1986.

Very truly yours, t c. G ,. O W. G. Counsil By: M D.R. Woodlan Licensing Supervisor JCH/gj c-NRC Region IV (0 + 1 copy)

Director, In'spection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIMION OF TEXAS LTELITIES ELECTRIC COMPANY

n- .-.

Log # TXX-4626 TEXAS UTILITIES GENERATING COMPANY File # 10110 SKYW AY TOWEB

• 400 NORT,8 OtJVE WFREET.1.B. e B .13 A3J.As. TEXAe 7330 3 November 20, 1985 u w n,

.. .m.m... .a..c.o..u..

p# Mr. R. P. Denise, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX. 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NO. 50-445 UPPER LATERAL RESTRAINT EMBEDMENT DESIGN QA FILE: CP-85-26, SDAR-187

Dear Mr. Denise:

On July 19, 1985, we verbally notified your Mr. D. Powell of a deficiency regarding the deviation from FSAR criteria in the design of the Unit 1 Steam Generator upper lateral restraint embedment. We have submitted an interim report logged TXX-4532, dated August 9, 1985. The concern is being evaluated under CPRT Program Plan Item V.b.

L We are continuing our evaluation and anticipate completion by January 22, 1986.

Very truly yours,

. i O. c,. W W.-G. Counsil By:

D. R. Woodlan Licensing Supervisor JCH/grr c- NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIY1SiON OF TEXAS L*2TLTTTES ELECTRIC COMPANY

u' Log # TXX-6030 File f 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SEYWAY N . 480 BeOST98 OLIVE N. La. 88 . DA1AAS, TEMAS Tumet October 20, 1986 i.'.YC. *J?E.h Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N0. 50-445 ELECTRICAL RACEWAY SUPPORT SYSTEM SDAR: CP-85-31 (INTERIM REPORT)

Dear Mr. Johnson:

4

, On August 27, 1985, we verbally notified your Mr. D. Hunnicutt of a deficiency involving the impact on the electrical raceway support system due to additional weight imposed by the installation of Separation Barrier Material (SBM) and Radiant Energy Shield (RES) Material on Unit I electrical conduit raceways without complete interdisciplinary review and design analysis. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our latest interim report, logged TXX-4883, was submitted on June 27, 1986.

The scope of this issue is limited to Unit 1 Electrical Conduit Raceways. The impact of SBN weights imposed on Unit 1 Cable Tray Hanger (CTH) Systems is being evaluated as part of the overall CTH design verification activities addressed by SDAR-CP-85-35, Cable Tray Hanger Design.

SBM and RES material were installed on Unit 1, Class lE electrical raceways consistent with the FSAR and Regulatory Guide 1.75, Revision 1. The engineering evaluation, prior to SBN t.nd RES material installation, did not i consider the additional weight imposed by these materials.

Although this concern is not a specific CPRT program plan item, the evaluation and disposition of this issue is being formulated in the course of the

civil / structural design verification program outlined in CPRT Program Plan Item, DSAP VIII.

Failure of seismic category conduits and conduit supports to meet the required design criteria could result in an inability of associated safety-related systems to perform as required for safe operation and shut down.

, 4 SfvEggoN OF TEXAS fjfflJ73ES EEXCTRN" COAdPANY

October 20, 1986 Page 2 Currently, we have identified the conduit raceways affected by the ,

installation of RES material. Our identification of the raceway population '

affected by the presence of SBN is incomplete. The evaluations completed to  !

date indicate the conduit and supports are adequate when considering the additior.al weight imposed by the protective materials.

Based on the project schedule for these engineering activities, we anticipate submitting our next report by December 5, 1986.

Very truly yours, i

W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies) -- .

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 f

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File a 10110 j 903.9 l l

TEXAS UTILITIES-GENERATING COMPAhT

.1.u.....o _ ..r m . .,..

. _ , ,o - .. . I June 27, 1986 C.'W:0,*.i",?.1% l Mr. Eric H. Johnson, Director Division of Reactor Safety and Projacts U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO 30-445 ELECTRICAL RACEWAY SUPPORT SYSTEM SDAR: CP-85-31 (INTERIM REPORT)

Dear Mr. Johnson:

On August 27, 1985, we verbally notified your Mr. D. Hunnicutt of a deficiency involving the impact on the electrical raceway support system due.to additional weight imposed by the installation of separation barrier and radiant energy shield material. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted interim reports logged TXX-4564, TXX-4599, and TXX-4672, dated September 19, 1985, October 16, 1985, and January 22, 1986, respectively.

This issue is currently being evaluated under CPRT Program Plan Item VIII.

Ebasco has consolidated all electrical raceway items (cable trays, conduit, and supports) under the scope of a single program which is scheduled to be completed in September, 1986. We are continuing our evaluation and anticipate submitting our next report by October 21, 1986.

Very truly yours,

/ 17b W. G. Counsil JCH/arh c - NRC Region IV (0 + 1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DTVISION OF TEXAS UTIIJTIES ELECTRIC COMPANY l

Log # TXX-4577 TEXAS UTILITIES GENERATING COMPANT File # 10110

..vw4r ro . . ~o- ouv= ==n. .. . . . . u .. ,=u moi October 1, 1985 33%# a.*.if.7.5 Mr. R. P. Denise, Director Divison of Reactor Safety and Projects Reactor Project Branch 2 U.S. Nuclear Regulatory Commission Office of Inspection'& Enforcement 611 Ryan Plaza Drive, Suite 1000

. Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 NON-SEISMIC TO SEISMIC INTERACTIONS QA FILE: CP-85-33, SDAR-195

Dear Mr. Denise:

On Septomoer 6, '1985 we veroally notified your Mr. C. Gould' of a deficiency regarding the project program for identifying non-seismic to seismic interactions that did not require the' evaluation of large equipment masses in two-inch and less piping.

We have completed our investigation and concluded that.the matter is not reportable under 10CFR50.55(e). Records supporting this determination are availaole for your inspector's review at the CPSES site.

Very truly yours, a , 7 )

/ RLt '

W. G. Counsil JCH/grr

c- NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

.s estV8%I60% trY TI:\ A% L'TRUTIE% EL2:CTNIC CtB\tPANY f ... . . . . . . _ . . . _ . . , _ _ . . _ . _ _ _ . _ . . _ _ , _ _ _ . _ . _ , _ _ _ . _ ,

Log # TXX-6047 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SEYWAY TOWER 4se NORT96 OLIVE STREET. Ls. et . DALLAS TEXAS 78301 October 21, 1986 i,'tl%".LU.n*L Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 CONDUIT SUPPORT DESIGN SDAR: CP-85-34 (INTERIM REPORT)

Dear Mr. Johnson:

On September 6,1985, we verbally notified your Mr. C. Gould of a deficiency involving the adequacy of conduit supports to perform their intended design functions. Our latest interim report, logged TXX-4805, was submitted on May 16, 1986. We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.

DESCRIPTION The seismic conduits and conduit supports at CPSES, Unit 1, are segregated i into Trains A, B and C. Conduit supports on Trains A and B are Seismic Category I. Train C conduit supports are non-seismic except for conduits larger than 2 inches in diameter and those supports which are Seismic Category II and either seismically designed or seismically restrained with aircraft cables. Non-seismic designed conduits are not within the scope of this issue.

Seismic conduit and support design is governed by design package S-0910 for r Unit I and Common areas. This document describes various types of l " engineered" and " generic" supports and allowable conduit spans. Supports l deviating from generic support criteria are identified as " Modified" or j " Individually Engineered" (IN) supports. These conduit supports were initially installed as field run systems supported in accordance with Gibbs &

Hill Drawing 2323-S-0910.

l The S-0910 design package was generated in general conformance with industry practices. However, a number of potential design concerns related to conduit supports have been identified through' external design review. These reviews resulted in several concerns regarding the adequacy of the conduit supports to perform design functions. In order to resolve these issues a 100%

verification of the conduit system design is being conducted in accordance

( with CPRT Program Plan Item DSAP VIII.

I

TXX-6047 October 21, 1986 Page 2 of 2 SAFETY IMPLICATIONS Failure of seismically designed conduits and conduit supports to meet the design criteria could result in an inability of associated safety-related systems to perform as required for safe operation and shutdown.

i l

, CORRECTIVE ACTION  :

! The identification and as-built configuration of conduit and conduit supports affected by the revised design criteria of S-0910 is currently ~being established through field verification. Demonstration of the adequacy of, or alternatively, identification of configurations requiring further study or modification is being accomplished through analysis of the field verification data.

Unistrut and transverse supports have been examined differently than in the i

above mentioned verification activity. For Unistrut supports, a Unistrut Test Program was implemented to determine the adequacy of Unistrut supports with regard to torsional loading'. Any Unistrut support determined from test to have capacities below those given in the original S-0910 package or not tested -

will be replaced or will be demonstrated to be not needed. All transverse supports will either be converted to multidirectional supports or will be demonstrated to be not needed.

l Completion of these programs is currently scheduled for February 2,1986. We anticipate submitting our next report by February 27, 1987.

Very truly yours, W. G. Co s1 By:

G. S. Keeley _ /

Manager, Nuclear L nsing JCH/amb c - NRC Region IV (0 + 1 copy)

( Director, Inspection & Enforcement (15 copies)

{ U. S. Nuclear Regulatory Commission l Washington, D.C. 20555 l

l

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t h- -o Loge TXX-4681 lL TENAS UTILITIES GENERATING COMPAAT Files 10110 f o . m . .. . ..

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a v w es e s es.e -

Janua ry 31, 1986 i

f1r. Eric H. Johnson, Acting Director Division of Reactor Safety and Projects U.S. iiuclear Regulatory Co rnission 611 Ryan Plaza Drive, Suite 10C0 Arlington, TX 76012

SUBJECT:

COMAf1CHE pears STEAll ELECTRIC STATI0ft- i t

DOCKET T10, 50-445 C0t'DUIT SUPPORT DESIGft SDAR: CP-85-34 1

1 s

Dear f1r. -Johnson:

1. i i :i On Seatember 6, 1985, we verbally notified your'Mr. C. Gould of a

~ i deficiency regarding the adequacy of conduit' supports to perform l l their intended design functions. 'This is an interim report of a-- ,

ootentially recortacle item under the provisio'ns of 10CFR50.55(e).  ;

- We have submitted an- interim report ' logged TXX-4571, dated September  ;

30, 1935. This. issue is'being evaluated under the CPRT Program Plan -

. Item VIII and is schedulea for resolution by April 25,:1986.

We are_ continuing our evaluation' and anticipate completion of our final . report by liay 16, 1986~. I 1  !

[

Very truly yours, ,

/ ' (, l't 7!.7 t f

W.G. Counsil JCH/gj

{- c - IIRC Region IV (0 + 1 copy) i Director, Inspection f. Enforcement (15 copies)

. U.S. Iluclear Regulatory Commission ,

Washington. 0.C. 20555 ~

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.I' Log # TXX-6048 File # 10110 903.9 TEXAS UTILITIES GENERA'ITNG COMPAhT i SETWAY TOWEB . 400,80ETH OEJYE STERET. LB. e e . DALLAS. TEXAS 78901 October 21, 1986 ,

EM*:S?AY."&h Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects .,

U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 AND 50-446 CABLE TRAY HANGER DESIGN  !

SDAR: CP-85-35 (INTERIM REPORT)-

Dear Mr. Johnson:

On September 6,1985, we verbally notified your Mr. C. Gould of a deficiency involving the design and construction activities of the cable tray hanger program. Our latest report, logged TXX-4884, was submitted on June 27, 1986.

We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.

DESCRIPTION j Cable tray supports were originally installed in accordance with general 1 criteria including standard support designs and associated guidelines based on  !

tray configurations, loads, and span lengths. The criteria were based on equivalent ste:i: analysis methods for assessing seismic loads. Where field l conditions preciuded the application of standard designs, design changes were i

. reviewed, approved, and issued as qualified specific support designs.

As a result of design and construction related concerns raised by external-sources, EBASCO and IMPELL have been directed to perform a 100% verification of the cable tray system design. These design activities are being conducted in accordance with CPRT Program Plan Item DSAP VIII, which includes third-party overview to assure resolution of the issues and compliance to licensing commitments.

Evaluation of this issue has progressed to the stage that modifications of some supports are. required to meet the FSAR criteria. Since the program implements required modifications, no evaluation has been performed of the safety consequences had these potential deficiencies remained undetected.

This item is applicable to Units 1 and 2.

SAFETY IMPLICATIONS Failure of seismic category cable tray supports to meet the required design criteria could result in an inability of associated safety-related systems to perform as required for safe operation and shutdown.

A DFVISION OF TEXAS t/TIEJTIES EXECTRfC CoadPANY

- _ - - . _ . _ .- - _. - .- . _ - _ _ _ . - _\

TXX-6048 October 210 1986 Page 2 of 3 CORRECTIVE ACTION The verification program is being implemented for Units I and 2. The primary difference between the two units is related to the inaccessibility of. hardware for Unit I due to the advanced state of construction.

For Unit 1, a number of the support design attributes are inaccessible as a result of congestion or the presence of fire protection material. Our approach in the development of these as-built drawings is as follows:

0 As-designed drawings have been developed for each support. These drawings are based on the original design and include design changes generated in the construction / design process.

O Field walkdowns have been performed using the as-designed drawing.

For all accessible supports and accessible portions of partially inaccessible supports, as-built conditions were confirmed or noted as different on the as-designed drawing. Final as-built drawings were produced specifically noting any items within the scope of the walkdown that were inaccessible. Quality Control verification of as-built drawings is currently in process.

O Span sketches (noting span lengths) have been developed based on field inspections of Unit I supports.

For Unit 2, where almost all attributes are accessible, as-built verification is being accomplished by direct field inspection of design attributes and the production of as-built drawings for each support.

Unit 2 design verification is performed using maximum cable tray fill weights, and conservative assumptions regarding the weight of fire protection material.

The equivalent static analysis method is typically used to determine support loads. The response spectrum method is being used to justify limiting the scope of modifications that would be difficult to implement in a congested environment.

Design verification based on as-built conditions is currently in process. The basis for' design review of inaccessible items for Units I and 2 has been addressed and documented in specific studies or reports.

For both units, loading combinations and stress limits are checked in accordance with acceptance criteria which conforms to CPSES licensing commitments.

A testing program has been established to augment the cable tray support verification effort. -The testing program is anticipated to be complete in November, 1986. Evaluation of the test results should be performed by late December, 1986.

. TXX-6048 October 21, 1986 Page 3 of 3 The design verification program addresses all cable tray support issues in an integrated manner. It will confirm that the design criteria is met or result in modifications to conform with design criteria. A number of modifications (approximately 800 hangers) have .already been implemented in Unit 2 and a significantly lesser amount of hangers in Unit 1 have been identified as requiring potential modifications. To achieve qualification, all modifications will be inspected for as-built conditions and the design will be verified.

Based on the projected schedules for testing and engineering evaluations, it is anticipated that our.next report will be submitted by January 30, 1987.

Very truly yours, 1

W. G. Coun i By: ,

G. S. Xeeley 1-/

Manager, Nuclear Qcensing JCH/amb c - NRC Region IV (O'+ 1 copy)

Director,- Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 1

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File

• 10110 903.9 l TEXAS IJTILITIES GENERATING COMPA.T N SKYW AY TOWEB . 400 NORT95 OLIVE STREET. L.B S t

• D AIJ.AS. TEXAS 7530 I June 27, 1986

.'"nS'J a,*.?f.7.5 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuc' ear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMAtlCHE PEAK STEAM ELECTRIC STAT'ON (CPSES)

DOCKET t10. 50-445 CABLE TRAY HANGER DESIGN SDAR: CP-85-35 (INTERIM REPORT)

Dear Mr. Johnson:

On September 6,1985, we verbally notified your Mr. C. Gould of a deficiency involving the . design and construction activities of the cc' ale tray hanger program. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted interim reports logged TXX-4573 and TXX-4673, dated September 30, 1935, and January 22, 1986, respectively.

This issue is currently being evaluated under CPRT Program Plan Item VIII.

Ebasco has consolidated all electrical ~ raceway items, including cable tray hangers, under the scope of a single program which is scheduled to be completed in September, 1986. We are continuing our evaluation and anticipate submitting our next report by October 21, 1986.

Very truly yours,

/W W. G. Counsil JCH/arh c - NRC Region IV (0 + 1 Copy)

Director,-Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commis'. ion Washington, D.C. 20555 i

i i

A DIVISION 07"TEXA 9 LTIIJTTE.9 ELECTEJC COMPANY I

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Log # TXX-5041 File # 10010 903.9 TEXAS UTILITIES GENERATING COMPAW SKYWAY TOWEB . 400 NORTH OLIVE WTMEET. I.B. 31. DALLAS. TEXAS 78208 October 3, 1986

.2% .*fl.".*.S Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N0. 50-445 TRAIN C CONDUIT SUPPORTS SDAR: CP-85-36 (INTERIM REPORT)

Dear Mr. Johnson:

On September 6,1986, we verbally notified your Mr. C. Gould of a deficiency involving the installation of non-safety related conduit (two-inch diameter.

and smaller) on non-safety related dead weight supports in Category 1 areas.

This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our most recent interim report was logged TXX-4974, dated August 22, 1986. We received an extension until October 3, 1986, frc:n your Mr. T. Westerman for submitting this report.

This issue is being evaluated by Impell under.CPRT Program Plan ISAP I.c.

Field verifications are currently in progress to verify the adequacy of these Train C conduit supports. Impell Corporation has developed a multilevel screening process which is being implemented to qualify all supports for seismic loads or to verify that adverse interactions with safety-related features do not occur. For supports that cannot be verified as acceptable for seismic loads, one of several rework options may be employed. These rework I options are to modify the support, reroute the conduit, or provide seismic restraints, t This program is currently underway for Unit I and Common Area. Approximately 35,000 conduit supports have been deemed acceptable for sei:mic loading, representing approximately one-half of the supports in Unit I and Common Area.

To date, the evaluation of 40 rooms has been completed and no safety hazards have been identified. This represents approximately 15 percent of the rooms in Unit 1 and Common.

This evaluation is currently scheduled for completion during the second quarter of 1987. We anticipate submitting our next report on this issue no later than January 21, 1987.

Very truly yours, i

W. G. Counsil JCH/amb A virssuos or rexas emunes es.ecrmc cmsexxr d

Log # TXX-4633 TEXAS UTILITIES GENERATING COMPANY Fi1e # 10110 SKYW AY TOwEn a 40e NORT1. OLIVE NTREET. L.B. 8 8 . DALLAS. TEXAS 78301

."1%78c.*A".751 November 26, 1985 Mr. Eric H. Johnson, Acting Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 FLUX MAPPING SEAL TABLE RESTRAINTS QA FILE: CP-85-40, SDAR-202

Dear Mr. Johnson:

In accordance with 10CFR50.55(e), we are submitting the enclosed written-report of actions taken to correct a deficiency regarding the adequacy of restraints (provided for the flux mapping system) under seismic loads.

Supporting documentation is available at the CPSES site for your Inspector's review.

Very truly yours,

, ,f?

W. G. Co'unsil JCH/grr Attachment c- NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 1

i A otviSION OF TEXAS LTTTl2 TIES ELECTRIC COMPANY t _

ATTACHMENT FLUX MAPPING SEAL TABLE RESTRAINTS DESCRIPTION The NSSS Supplier (Westinghouse) has advised of a possible system interaction involving the Flux Mapping System (FMS) and the Seal Table / Bottom-Mounted Instrumentation. Specifically, portions of the FMS which are designed and fabricated non-safety related are located directly above the seal table. The seal table.is the pressure boundary. Failure of non-safety portions of the FMS or parts thereof falling on the seal table could result in a breach of the pressure boundar3 Review by the NSSS Supplier has confirmed the FMS restraints are inadequate for the seismic loads postulated for a seismic event.

SAFETY IMPLICATION In the event the condition had remained undet'cted, e the potential exists for a small break loss of coolant accident.

CORRECTIVE ACTION A detailed analysis has been performed which indicates adequate restraint can be provided for the FMS. Currently, the Supplier is reviewing comments to the proposed modifications provided by site engineering. The resolution of these comments and actual modifications to the FMS are expected to be completed March 31, 1986.

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Log 0 TXX-4716

. File # 10110 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NORTH OI.JVE EFTMEET. L.B. a 8

• DALLAS TE3LAS 78201 February 28, 1986 ThM*:h?.9? .ib Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION

' DOCKET NO. 50-446 COMPUTER PROGRAM ERRORS SDAR: CP-85-41 (FINAL REPORT)

Dear Mr. Johnson:

On September 18, 1935, we verbally notified your Mr. T. Westerman of a deficiency involving errors. identified in checking routines of computer program P Delta STRUDL 0385. The program is used by an engineering contractor in the analysis of cable tray and conduit supports for Unit 2.

We have submitted interim reports logged TXX-4614 and TXX-4590, dated November 7, 1985, and October 10, 1985,-respectively.

Computer routines for approximately 1,000 of 3,800 affected calculation packagespotentiallyaffectedbytheprogramerrorshavebeenrerun. This sample has not identified a single support where the errors have had an adverse effect on the integrity of the cable tray supports. ~The issue is not reportable under the provisions of 10CFR50.55(e). Records supporting this determination are available for your inspectors to review at the CPSES site.

Very truly yours, Wa0 W. G. Counsil JCH/ arm c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEVISION OF' TEXAS UT112 TIES ELECTRIC COAtPANY

Log # TXX-6049

- * ~'

File # 10110-903.9 TEXAS UTILITIES GENERATING COMPANY

.MWAY N ese ,00MN OUVE STREET. I.B. S 8

• DAM.AS. TEXAMSSSI October 21, 1986

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Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 THERM 0 LAG ON CONDUIT SUPPORT SDAR: CP-85-42 (INTERIM REPORT)

Dear Mr. Johnson:

On September 20, 1985, we verbally notified your Mr. T. F. Westerman of a deficiency involving the possible adverse effect of the substitution of rectangular and oversized pre-formed sections of thermolag on conduit installations. Our latest report, logged TXX-4806, was submitted on May 16, 1986. We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.

DESCRIPTION Thermolag fire protective coating was installed on Unit 1, Class IE Electrical conduit Raceways consistent with FSAR and Regulatory Guide 1.120, Revision 1.

In the original design, fire protection weight was assumed considering a round configuration of thermolag material around conduits. However, to facilitate adequate coverage of field run conduits, thermolag in square configurations has been substituted in some locations. Without engineering verification to determine if square shapes were enveloped by the design assumptions, field verifications have been conducted to provide as-built information regarding thermolag size and shape installations. This data has been evaluated and l resulted in the identification of several instances of excessive loading of-conduit and inadequate conduit support. In these-instances, the stresses are l in. excess of allowable due to conduit couplings installed between supports.

t This issue is being evaluated under CPRT Program Plan DSAP VIII and is limited to Unit 1 electrical conduit raceways and supports.

SAFETY IMPLICATIONS Failure of seismic category conduits and conduit supports could result in an inability of associated safety-related systems to perform, as required, for safe operation and shutdown.

l l

A DEVIs#ON OF TEXAS UTIIJTIES ELECTMIC COAEPANY

>=

TXX-6049 October 21, 1986 Page 2 of 2 i CORRECTIVE ACTION Engineering analysis will continue for affected conduits, supports and associated appurtenances such as junction boxes. The final evaluation and corrective actions include additional testing activities currently underway and additional review by the Fire Protection Group to confirm the necessity for thermolag installation. These activities are currently scheduled for completion on November 17, 1986.

Revised engineering and construction requirements have been issued to prevent recurrence of this deficiency.

We' anticipate submitting our next report December 15, 1986.

Very truly yours, W. G. Co n i d

, , By:

G'. S. Keeley ~ / __

Manager, Nu icensing JCH/amb

. i'

+E

, c - NRC Region IV (0 + 1 copy)~

7 Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission ~

Washington, D. C. 20555 i

i l

i I

- Log # TXX-4675 TENAS UTILITIES GENERATING COMPANYFi1e # 10110 EKYWAY TOWER

• 400 NORTit OLIVE STREET. L.B. el

• DALLAS. TEJLABB T5205 January 22, 1986

,'A%71NT."a'A Mr. Eric H. Johnson, Acting Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAR, STEAM ELECTRIC STATION DOCKET NO. 50-445 THERM 0 LAG SDAR: CP-85-42

Dear Mr. Johnson:

On Septemoer 20, 1985, we verbally notified your Mr. T. Westerman-of a deficiency regarding the possible adverse effects of sucstituting' pre-formed sections of tnermolag on conduit and conduit support installations. Tnis is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We nave suomitted an interim report logged TXX-4572, dated OctoDer 16, 1985. The evaluation and disposition of this issue will be formulated in the course of tne conduit and caole tray design adequacy programs _(CPRT Program Plan Item VIII). Tne analysis required to resolve this issue is scheduled for completion by April 25, 1986.

We are continuing our investigation and anticipate completion of our final report by May 16, 1986.

Very truly yours.

O4 W. G. Counsil By: D' '

O.R. Woodlan Licensing Supervisor JCH/gj c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIY1SION OF TEXAS UTILETIES ELECTRIC COMPANY

Log # TXX-4591 TEXAS UTII.ITIES GENERATING COMPANT Fi1e # 10110 isKYW AY TOWER

• 400 NORTlt DIJVE SFTREET. L.M. S S

• DALLAS. TEXAM 7820 8

.'*f;Yllic?2f.7.".S October 10, 1985 Mr. R. P. Denise, Director Division of Reactor Safety and Projects Reactor Projects 5 ranch 2 U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 0UALIFICATION OF PLANT TEMPERATURES QA FILE: CP-85-43, SDAR-205

Dear Mr. Denise:

On September 20, 1985 we verbally notified your Mr. T. F. Westerman of a defi_ciency involving an inconsistency between plant temperatures for normal modes of operation published in the FSAR and temperatures considered in environmental equipment qualification.

.s We are continuing our evaluation and anticipate completion by December 31, 1985.

Very truly yours,

, o s ,

l / b; :7:04 W. G. Counsil JCH/grr.

c- NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

.s ,,,s is,os or rex.s.s criurses ru:< tmc cmreA.s,

,. -Log ! TXX-4656 TEXAS UTILITIES GENTRATING COMPANY Fi1e ! 10110 aKYwAY TowEm . 400 NORTH 08JVE PrTREET. L.R. S B . DALLAS. TEXAS 78201

.'"AS70Mf0'.S -December 20, 1985 Mr. Eric H. Johnson, Acting Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Dri.ve, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 MAIN STEAM LINE FLUID TRANSIENT SDAR: CP-85-49

Dear Mr. Johnson:

In accordance with 10CFR50.55(e), we are suomitting the enclosed written report of actions taken to correct a deficiency regarding the Auxiliary

, Feeddater (AFW) turbine steam supply line. On December 6, 1985 we verbally notified your Mr. S. Phillips of this potentially reportable issue.

Evaluation of this issue has identified a reportable condition under the provisions of 10CFR50.55(eTinvolving the piping and support systems for the main steam supply line to the AFW turbine.

Very truly yours, ,

q')

f l . 7 LOV/ LOC

'l W. G. Counsil JCH/grr Attacnment c- NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)-

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A L)lV8 MON OF TEXAS L*TilJTIES CtZLTRIC COMPANY

. ATTACHMENT MAIN STEAM LINE FLUID TRANSIENT DESCRIPTION In the process of: evaluating a problem report issued by operations engineering regarding damaged snubbers, a design concern was observed in two (2) main steam piping systems.. As a result of steam condensation and inadequate provisions for draining, moisture accumulation creates an unevaluated fluid transient (or waterhammer).

The specific lines are installed in parallel originating at the steam

~

generator (numbers 1.and 4) main steam headers upstream of the main steam isolation valves. The piping terminates at the auxiliary feedwater pump turbin~e. Thermal _ movement resulting from the fluid transient could exceed design stresses considered in the piping and support design, and result in damage to attached components.

The concern is applicable to Units 1 and 2.

SUMMARY

OF EVENTS  ;

Date Discovered: May 16, 1985 by Problem Report 85-297 Date Identified as Potentially Reportable: November 6, 1985 Date NRC_hotified as Potentially Reportable: ' December 6, 1985 Date Determined Reportable: December 18, 1985 SAFETY IMPLICATION' In the event the condition had' remained undetected, the capability of the piping'and associated support system to perform the intended safety -

functions could not be assured.

CORRECTIVE ACTION In order to implement measures to remove moisture accumulation, the

. piping systems will be redesigned to include sloping and additional drain pots. Reanalysis of the piping and support scheme will be performed in conjunction with the issue of system rework documents.

The Unit 1 and 2 engineering efforts are scheduled for completion in May and July of 1986 respectively. Construction activities will follow itraediately in Unit I and as determined in the construction scnedule for Unit 2.

j Fil$7 10110 908.3 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NORT,8 OL2VE FrREET, t a. 8 4 . DA11AS. TEXAS 7820 8 June 27, 1986 W: .%'.??,'.T:-

Mr.'Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. fluclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO3. 50-445 AND 50-446 CABLE TRAY TEE' FITTINGS SDAR: CP-85-50 (INTERIM REPORT) ,

Dear Mr. Johnson:

On December 6,1985, we verbally notified your Mr. H. S. Phillips of a oeficiency involving the use of improper welding processes in the manufacturing of cable tray tee fittings which could affect the equipment qualification.

This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted interim reports logged TXX-4663 and TXX-4713, dated January 6, 1986, and February 26, 1986, respectively.

The qualification of cable trays is directly related to the design verification efforts currently assigned to Ebasco and Impell. Ebasco has consolidated all electrical raceway items under the scope of a single program with the evaluation and identification of corrective actions scheduled ta be completed in September, 1986. We are continuing our evaluation and anticipate submitting our next report by October 21, 1986.

Very truly yours, W. G. Counsil JCH/arh c - NRC Region IV (0 + 1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DTV2SION OF TEXAS L*TIIJTIES ELECTRIC COMPA.%T

s -

e Log # TXX-4657 TEXAS UTILITIES GENERATING COMPAM File # 10110 SKYWAY TOWER . 400 NORT,6 UL.IVE STREET. EA S S

• DAI 1.AS.1 EX.A5 7530 3

.".'EMe.*S.".7.D December 20,-1985 Mr. Eric H. Johnson, Acting Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET N0. 50-445 CABLE TRAY HANGER REVERIFICATION PROGRAM SDAR: CP-85-52

Dear Mr. Johnson:

In accordance with 10CFR50.55(e), we are submitting the enclosed written report of actions taken to correct a deficiency regarding tne Cable Tray Hanger Reverification Program. On December 18, 1935 we verbally nctified your Mr. T. F. Westerman of this issue and that it was cetermined to ce reportaole under the provisions of 10CFR50.55(e). .

Very truly yours, bTl)

W. G. Counsil JCH/grr Attachment c- NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington. D.C. 20555 s , ., v, <,, . v , . c rr n v , rr , e r, r s r , r, , . .. . . . . . - . v ,

~

.i ATTACHMENT CABLE TRAY HANGER REVERIFICATION PROGRAM DESCRIPTION In order to assess the significance of earlier concerns regarding design and construction adequacy, a field verification and inspection program

_. has been initiated for cable tray hangers. Using this as-built information, an analysis would be performed to attest and revalidate the structural integrity of the support system. . A recent review of field efforts has identified discrepancies and inconsistencies which, if undetected, could invalidate the analysis.

The concern is applicable to Unit 1. ,

SUMMARY

OF EVENTS Date 6iscovered: November 27, 1985 by Corrective Action Request (CAR)-053 Date Identified as Potentially Reportable: December 17, 1985 Date Determined Reportaole: December 18, 1985 Date NRC Notified as Reportable: December 18, 1985 SAFETY IMPLICATION In the event this condition had remained undetected, the support of electrical conductors essential to safe plant operation could not be assured.

CORRECTIVE ACTION Verification and inspection activities will be reperformed. These actions will be accomplished by personnel recently trained in appropriate program documents. These actions and the associated analysis will be completed prior to fuel load. Specific detailed corrective actions will be documented in the site-initiated CAR-053.

\

L s I

.\

Lcg # TXX-5042 File # 10010 903.8 TEXAS UTILITIES GENERATING COMPANY SKYWAY Towsm . 400 NORTH O1JVE STREET. L.B. 81. DALLAS. TEXAS 7890 8 September 26, 1986 l

S7A",^Ue??Ja*S Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SEISMIC CATEGORY II PLATFORMS SDAR: CP-85-53 (INTERIM REPORT)

Dear Mr. Johnson:

On December 20, 1985, we verbally notified your Mr. R. Hall of a deficiency involving Seismic Category II platforms. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted interim reports logged TXX-4669, TXX-4857, and TXX-4942, dated January 20, 1986, June 13,.1986, and July 30, 1986, respectively.

Currently, we have identified the platforms within the scope of this issue.

Documentation packages will be assembled for each item which will be used in the preparation of specific instructions for additional inspections. Our evaluation of this deficiency will be based upon review of the inspection results.

The above actions are currently scheduled for completion by December 29, 1986.

We anticipate submitting our next report by January 30,-1987.

Very truly yours, S

W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A DEVISION OF TEXAS UT112TTES ELECTRIC COMPANY

.'

• Log # TXX-5043 File # 10010 903.7 TEXAS UTILITIES GENERATING COMPAhY SEYWAY TOWEE . 400 NORTH OLIVE WTMEET. L.B. 8 4 . DAELAS. TEXAS 75308 September 26, 1986 Ch??"h.*?E.".*.h Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SEISMIC QUALIFICATION OF HVAC SUPPORTS SDAR: CP-85-54 (INTERIM REPORT)

Dear Mr. Johnson:

On December 20, 1985, we verbally notified your Mr. R. Hall of a deficiency involving discrepancies in supplier provided HVAC support documents which could invalidate the seismic qualification of the supports. We have submitted~

interim reports logged TXX-4668, TXX-4718, and TXX-4863 dated January 20, 1986, February 28, 1986, and June 18, 1986, respectively. We are reporting this deficiency under the provisions of 10CFR50.55(e)'and the required information is attached. Our evaluation of this issue is continuing and we anticipate submitting our next report by November 20, 1986.

Very truly yours, 4

I W. G. Counsil JCH/amb Attachment c.- NRC Region IV (0 + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l

A DEVIS10N OF TEXAS UTTLETTES ELECTRIC COMPANY

TXX-5043 9/26/86 Page 1 of 2 ATTACHMENT SEISMIC QUALIFICATION OF HVAC SUPPORTS DESCRIPTION During a program review of documentation by Site Engineering, discrepancies were found in Unit I and Common HVAC duct support documents provided by the supplier (Bahnson). The discrepancies involved inconsistencies between as-built support drawings, actual installed conditions, and the seismic qualification calculations. The validity of the seismic qualification report could not be determined, pending further investigations.

In order to resolve this issue, a program of as-built verification inspections and engineering evaluations of selected Seismic Category I duct supports was initiated. Duct layout and support configuration inspections were conducted to obtain the actual as-built information needed to perform engineering evaluations of the supports. The engineering evaluations were performed to determine the qualification status of the installed duct supports and to identify potentially safety significant concerns.

Field verifications (as-built walkdowns) to obtain duct layout, duct support, and duct-to-support attachment details commenced in April 1986. Due to deviations in the as-built verification program for the duct supports as detected by TUGC0 QC surveillance activities, that portion of the as-built program was suspended in July 1986. This suspension of activities did not affect the field verification of duct layout and duct-to-support attachment details.

The as-built verification effort (based on the duct support sample in Unit I and Common which had been completed prior to the work suspension as well as the verified duct-to-support attachment details) has indicated numerous

. construction deviations from the intended design and/or the absence of design information for attachment details.

l Initial engineering evaluations of the limited sample have indicated that I although the specific design criteria may not be met as a result of the differences between as-built and as-designed conditions, the supports would not fail. Thus, no deficiencies have been identified to date which, had they remained uncorrected, could have adversely affected the safe operation of the HVAC supports.

However, these results to date are inconclusive because (a) the sample of supports upon which these results are based is too limited and (b) more detailed engineering evaluations may show that the original design criteria are met even with the construction deviations.

Because of the differences identified to date between as-built and as-designed HVAC supports, we have determined that a one hundred~ percent (100%) as-built effort is appropriate. This effort will be undertaken including a comprehensive design verification effort. Further engineering evaluations of the sample conducted to date have been superseded by the revised program l

described as " Corrective Action."

The scope of field verification, construction deviations from intended design, technical evaluation, and resulting rework, if any, is of a magnitude such that this issue is being reported under the provisions of 10CFR50.55(e).

l

< :,=  !

TXX-5043 9/26/86 Page 2 of 2 ATTACHMENT SEISMIC QUALIFICATION OF HVAC SUPPORTS

SUMMARY

QE EVENTS:

Date Discovered: December 20, 1985, per engineering documentation review Date NRC Notified as Potentially Reportable: December 20, 1985 Interim Reports to the NRC: January 20, 1986, February 28, 1986, and June 18, 1986 Date Reported: September 26, 1986 SAFETY IMPLICATIONS:

No definitive conclusions can be drawn on the safety of the HVAC supports in the event the differences between as-built and as-designed conditions had remained undetected. The limited engineering evaluation to date indicates no adverse effect on safe operation of the HVAC supports. The corrective actions

discussed below will ensure that the HVAC system will operate safely.

CORRECTIVE ACTION:

The following corrective measures are being implemented to resolve this issue:

. 1. The project organization and responsibilities for Unit I and Common HVAC activities have been realigned. Engineering and QC activities previously performed by Bahnson have been assumed by Ebasco and TUGCO, respectively.

The field verification effort has been expanded to encompass all 2.

Unit I and Common Seismic Category I duct supports.

3. Engineering evaluations will be performed to ensure compliance with j FSAR commitments.

f

4. Construction rework will be performed, as deemed necessary, by the engineering evaluations of field verified information to assure compliance with FSAR criteria for the affected supports.

5. To assure Unit 2 installations comply with prescribed requirements, Unit 2 HVAC supports will be field verified. The as-built effort will be conducted by Bahnson, with QC verification by TUGCO. Ebasco has been given responsibility for the adequacy of the as-built verification effort and design.

The revised project organization is scheduled to be formally established by September 29, 1986. The revised field verification, engineering evaluation, and rework (if required) program is currently scheduled for completion by May 1, 1987, for Unit I and September 1, 1987, for Unit 2.

In light of the extended schedule for completion of these activities, progress reports will be periodically submitted. Our next report will be submitted November 20, 1986.

lfi'le 0 20T10 903.7 TEXAS L'TILITIES GENERATING COMPANT SKYgy A Y TOWER . 400 NORTH OLIVE frTREET. L.lB. 51

• DA11AS, TEXAS TS201 June 18, 1986 0 3 .7 h N N A %

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SEISMIC QUALIFICATION OF HVAC SUPPORTS SDAR: CP-85-54 (INTERIM REPORT)

Dear Mr. Johnson:

.On December 20, 1985, we verbally rotified your Mr. R. Hall of a deficiency involving discrepancies in supplier provided HVAC support documents which could invalidate the seismic qualification of the supports. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

We have submitted interim reports logged TXX-4668 and TXX-4718, dated January 20, 1986, and February 28, 1986, respectively.

As built walkdowns started. in April,1986, to obtain duct layout, support layout, and duct-to-support attachment information and details. Engineering evaluations are in progress and are estimated to be completed in September, 1986. The scope of the work includes 415 of the approximately 3900 HVAC supports in Unit I and Common. The supports comprise the Diesel Generator Train A and B Systems (65 supports) and the Control Room HVAC Safety-related Systems (350 supports). All duct-to-support attachments in Unit I and Common (131C total) are included in the walkdown and engineering evaluation efforts.

We anticipate submitting our next report by September 26, 1986.

Very truly yours, l .

t

$ b 4/

l G. S. Keeley % /-

t Manager, Nuclear!d censing l

l JCH/arh

! c - NRC Region IV (0 + 1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEVISION OF TEXAS L*TILITTES ELECTEllC COMPA.W

Log # TXX-4718 File # 10110 903.7 TEXAS UTILITIES GENERATING COMP.-LYY SKYW AY TOWEB . 400 NORTH OIJVE STREET. L.B. e B

• DALLAS. TEXAS 75303

~ ~

February 28, 1986 UEJOSUA*A Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory _Conmission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 SEISMIC OUALIFICATION OF HVAC SUPPORTS SDAR: CP-85-54

Dear Mr. Johnson:

On December 20, 1985, we verbally notified your Mr. R. Hall of a deficien:y involving discrepancies in supplier provided HVAC support documents wnicn could invalidate the seismic qualification of the supports. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4668, dated January ~20, 1986.

A program of field inspections and engineering verification has been ini-tiated to determine the extent of this issue. As-built analyses of the support system in selected plant areas, in addition to the review of speci-fic hardware concerns, will provide information to assess the unresolved support qualification issue. These efforts are currently scheduled for completion in late May, 1986.

We are continuing our evaluation and anticipate completion of our final report by June 19, 1986.

Very truly yours,

/

l .

' i tii?47 W. G. Counsil JCH/ arm c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Wasnington, D.C. 20555 A DIVISION OF* TEXAS UTELETIES ELECTRIC COMPANY

Log # TXX-4723-File # 10110

- 910.4 TEXAS UTILITIES GENERATING COMPANT SKYW AY TowES . 400 NORT,. OLIVE STREET. L.B. 5 3 . DALLAS. TE3LA5 7S301 March-3, 1986

.7.tSCAf,0.".7.TA Mr..Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET N05. 50-445 AND 50-445 TURBINE-DRIVEN AUXILIARY FEEDWATER PUMP PERFORMANCE SDAR: CP-86-02 (FINAL REPORT)

Dear Mr. Johnson:

On January 9, 1986, we verbally notified your Mr. T. Westerman of a defi-ciency regarding a design change to the turbine-driven auxiliary feeawater pump which alters its performance capabilities. We have submitted an int.erim report logged TXX-4693, dated February 7, 1986.

Although original pump requiremente were reduced, corollary FSAR and craf t technical specification revisions have also been properly issued and approved. -The current system design has been found to satisfy the FSAR requirements and is capable of. performing its intended. safety function.

Had the deficiency remained uncorrected, it could not have adversely affected the safety of operations. Therefore, this issue is not reportable under the provisions of 10CFR50.55(e). Records supporting this aeter-Emination are available for your inspectors to review at the CPSES site.

Very truly yours,

! ./ (A?

W. G. Counsil JCH/ arm c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies) l U. S. Nuclear Regulatory Commission Washington, D.C. 20555 i

l A DIY1510N OF TEX AS UTILITIES ELECTRIC COMPANY

I Log # TXX-6031

' File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY

.EYWAY Nm . et ,00m OUVE MENT. LB. M , nas s am NAS MSM October 20, 1986 EE N.L U.2 %

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 PROXIMITY PLACEMENT - RICHMOND INSERTS TO EMBEDDED PLATES SDAR: CP-86-04 (INTERIM REPORT)

Dear Mr. Johnson:

i On January 13, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency regarding the placement of Richmond inserts in the proximity of loaded embedded plates which could compromise the structural integrity of adjacent shear cones. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted interim reports logged TXX-4700 and TXX-4919 dated February 12, 1986, and July 18, 1986, respectively.

Prior to March 3,1986, design and installation requirements did not identify minimum spacing requirements between loaded Richmond inserts and loaded embedded steel plates. As a result, conditions could exist in which the attached item (s) could have overlapping shear concrete cones and exceed the local structural design loading values. Our evaluation has revealed similar conditions exist for the spacing between Hilti bolts and loaded embedded plates. The scope of thir. evaluation is being expanded to encompass these conditions.

To prevent recurrence, specification 2323-SS-30, " Structural Embedments," has been revised and Construction Procedure Instruction CEI-20 is being revised to clarify concrete anchor-spacing criteria. Construction procedure CCP-45,

" Permanent and Temporary Attachments to Embedded Weld Plt.tes," has been  ;

revised to clarify installation criteria and construction attributes. Quality l Control Procedure QI-QP-11.14-13, " Separation Verification of Attachments to 1 Loaded Embedded Plates," has been developed to address the inspection of l attachments to embedded plates and spacing requirements for welded attachments,. loaded Hilti bolts, and Richmond inserts. This procedure will also address the inspection of previous and in-process installations.

4 d

< t- TXX-6031 October 20, 1986 Page 2 Due to the revised scope of this issue, the identification (through field verification and subsequent evaluation) of Unit 1 installations involving the spacing of anchors / attachments is, scheduled for completion by January 16, 1987. In Unit 2, the Wall Embedments and Beams (WEB) program will provide identification and analysis of all embedded plate attachments. A plan for the reinspection of existing Unit 2 embedded plate attachments is in development.

We anticipate submitting our next report no later than February 6,1987.

Very truly yours, W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 l

l l

l l

l l

. . - . , _ . . , _ , , - - _ , . , . .-_.-,.,,_,-y ..c... - , _ -

F 903.8 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWEB . 400 NORTH OIJVE STREET. L.B. S 8 . DALLAS. TEXA5 7820 8 July 18, 1986 1%7Afa"a5 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects ,

U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX .76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 PR0XIMITY PLACEMENT - RICHMOND INSERTS TO EMBEDDED PLATE SDAR: CP-86-04 (INTERIM REPORT)

Dear Mr. Johnscn:

On January 13, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency regarding the placement of Richmond inserts in the proximity of embedded plates which could compromise the structural integrity of adjacent shear cones. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4700, dated February 12, 1986.

We are continuing our evaluation and anticipate submitting our next report. by October 20, 1986.

Very truly yours, W. G. C ' s'l By: % < '

Man ger ti ing JCH/arh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15-copies)

U. S. Nuclear- Regulatory Commission Washington, D.C. 20555 A DIVISION OF TEXA5 L*TILETTES ELECTRIC COAtPANY

Log i TXX-4700 File # 10110

- 903.8' TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER e 400 NORTH OEJVE STREET. LB. El e DAI 8.AS. TEXAS 78301 February 12, 1986

?3'*2?2?.7.*%

Mr. Eric H. Johnson, Acting Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 PROXIMITY PLACEMENT - RICHMOND INSERTS TO EMBEDDED PLATE SDAR: CP-86-04

Dear Mr. Johnson:

On January 13, 1986, we verbally notified your Mr. T. Westerman of a deft-ciency regarding the placement of Richmond inserts in the proximity of embedded plates which could compromise the structural integrity of adjacent shear cones..'This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

Evaluation of the issue will require an assessment - by field survey - of all potential spacing violations involving Richmond inserts in the proxi-mity of embedded plates. At this point, the Unit 2 Safeguard builcing sur-vey results have been' completed without the ' identification of adverse conditions. Unit 1 efforts and the balance of Unit 2 efforts are scheduled to be completed by late June, 1986. Actions to preclude recurrence of the issue have been identified and are in preparation.

We are continuing our evaluation and anticipate completion of our final report by July 18, 1986.

• Very truly yours, 47LO W. G. Counsil JCH/ arm c - NRC Region IV.(0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIVISION OF TEXAS t.?Til2 TIES ELECTRIC CO%tPANY

Leg # TXX-4739 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NORTM OLIVE STREET 3 B. SS o DA12.Am. TEXA3 75308 March 25, 1986

."n = A*1".7.'A Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NO. 50-445 SAFETY CLASS PIPE SUPPORTS MOUNTED TO NNS EMBEDDED PLATE SDAR: CP-86 INTERIM REPORT

Dear Mr. Johnson:

On January 13, 1986, we verbally notified your Mr. T. Westerman of.a defi-ciency involving four piping systems which have been identified as

-including safety class pipe supports mounted to non-safety related embedded plates. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4701, dated February 12, 1986. Constraints involving testing inside the Unit 1 boundary for the remaining single support have delayed completion of our final report on this matter.

We are continuing our evaluation and anticipate completion of our final report-by April 25, 1986.

Very truly yours, W. G. Counsil JWA/ arm ,

c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEVISION OF TEXAS UTEL.1 TIES ELECTR2C COMPANY

Log i TXX-4701 File i 10110 903.8

- TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NORTH OLIVE snEET. L,3,, 3 5 . DALLAS. TEX.A5 7S301 February 12, 1986

.73%7Ah!.".7.'A Mr. Eric H. Johnson, Acting Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET N0. 50-445 SAFETY CLASS PIPE SUPPORTS MOUNTED TO NNS EMBEDDED PLATE SDAR: CP-86-05

Dear Mr. Jonnson:

On January. 13, 1986, we verbally notified your Mr. T. Westerman of a defi-ciency involving four piping systems which have been identified as including safety class pipe supports mounted to non-safety-related embedded plates. .This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Currently, with a single exception, all piping systems and supports have been analyzed without noting an adverse condition. The remaining support at issue will require re'moval of the sup-port and testing of the base plate.

We are continuing our evaluation and anticipate completion of our final report by March 25, 1986.

Very truly yours,

i

fi

'(,' A%f W. G. Counsil

^JCH/ arm c - NRC Region IV (0 + 1 copy)

Director, inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 a zurzssos or rexas vriuries ei.ccruze casurasr

Log 0 TXX-5026 File # 10110 909.2 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NORTH OI.JVE STREET. L.B. 8 I = DAI.J AS. TEXAS 78201 September 19, 1986 Miff"nO, Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission Gil Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION-(CPSES)

. DOCKET NOS. 50-445 AND 50-446 SERVICE WATER SYSTEM LEAKAGE SDAR: CP-86-07 (SUPPLEMENTAL REPORT) ,

Dear Mr. Johnson:

On April 11, 1986 we verbally notified you of a reportable item involving weld failure and coating degradation in the Service Water System (see TXX-4762).

i This is a follow-up supplemental report on a reportable item under the provisions of 10CFR50.55(e).

Our inspections of the Train "A" Service Water Piping have been completed revealing no generic failures of the Plasite coatings. Several pitted areas were identified for which repair was warranted. Other areas containing minor defects, iiot warranting repair, were identified and will be used as baseline data for future inspections.

Several design modifications are currently being implemented on Train "A" which are currently scheduled for completion by November 7,1986. Train "A" will be held out of service until these actions are complete. The inspection of Train "B" will not be started until Train "A" is returned to service. This inspection will require two months to complete. Therefore, corrective measures which may be required for Train "B" are scheduled for completion by January 15, 1987.

We anticipate completing our evaluation of the corrective action and submitting our next report by January 30, 1987.

Very truly yours, W. G. Co s1

/

By:

G. S. Keeley C /-

Manager,Licensity/

JCH/amb A DEVISION OF TEXAS UTELETTES ELECTRIC COMPANY

Log # TXX-4943 File - 10110 909.2 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NORTH OL2VE JT1tEET. L.B. 5 3 . DALLAm. TEXAS 78304 July 30, 1986 3.'M7 Aff.".7.".'.'.,

Mr. Eric H. Johnson, Directo'r Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000

- Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SERVICE WATER SYSTEM LEAKAGE SDAR: CP-86-07 (INTERIM REPORT)

Dear Mr. Johnson:

On April 11, 1986, we verbally notifed you of a reportable item involving weld failure and coating degradation in the Service Water System (see TXX-4762).

This is a follow-up interim report on a reportable item under the provisions of 10CFR50.55(e).

We anticipate completing our evaluation of the corrective action and suomitting our next report-by September 26, 1986.

Very truly yours,

/ $

W. G.-Counsil JCH/arh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEV1SION OF TE.%AS UTTZ.!TLES E22CTRIC COMPANY

f. ,

Log # TXX-4762 i ja F11e # 10110 909.2 TEXAS UTILITIES GENERATING COMPANY SKYWAY T(,wEm e 400 NORTH OtJVE STREET. L.M. 8I . DALLAS. TEXAm 7S308 April 11, 1986

.7.'MJAff.f.".'.S Mr. Eric H. Johnson, Director Division-of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX -76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 SERVICE WATER SYSTEM LEAKAGE SDAR: CP-86-07 (INTERIM REPORT)

Dear Mr. Johnson:

On January 24, 1986, we verbally notified you of a deficiency regarding weld failure and coating degradation in the Service Water System. We submitted an interim report TXX-4711 dated February 24, 1986. We have concluded that this deficiency is reportable under the provision of 10CFR50.55(e). We anticipate. evaluation of all corrective action and completion of our final report by July 30, 1986.

Very truly yours, b l W. G. Counsil JCH/grr Attachment '

c - NRC Reglan IV (0 + 1 copy)

Director,. Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 i

A Dit'ESSON OF TEX AN tJTILITIES ELECTRIC CU%tPANY l

I

T~

ATTACHMENT

, M SERVICE WATER SYSTEM LEAKAGE DESCRIPTION AND CORRECTIVE ACTION The-following is a description and corrective action for weld failure and coeting degradation deficiencies associated with the Station Service Water System.

The repeated weld failure in the vicinity of ISW-026 is caused from vibration fatigue. The lumped mass of instrument isolation valve ISW-026 is excited from flow induc'ed vibration at flow control valve ISW-022 and restricting orifice CPI-SWORFR-05. The short nipple connecting the valve and orifice flange has little flexibility and is a stress riser. The corrective action will be to lengthen the connected pipe nipple to add flexibility and thereby eliminate the stress riser.

In relation to the weld at the junction of 24-SW-003-150-3 and 1-SW-1 021-150-3, and the weld in the vicinity of valve ISW-023, it was established that erosion-corrosion associated with the cavitation across valve ISW-023 created the weld and pipe failure. In order to eliminate the erosion-corrosion concerns, the carbon steel pipe spool downstream of valve ISW-023 will be replaced with a flanged 316 stainless steel spool.

Field weld 10A in stainless steel line 2-SW-1-302-150-3 has been radiographed and an_ ultrasonic _ test performed on the surrounding area. The test results showed several small indentations existing in the pipe wall and a small cylindrical hole existing within its vicinity. A complete failure analysis will be performed on the weld when Train B is out of-service. The expected completion date of this analysis is June 1986. This weld has been temporarily patched to reduce water spray.

In regard to deterioration of the plastic coating, the piping will be repaired or recoated as necessary using a Belzona lining. The exact extent of the lining repair in Train A will be established from the recently completed lining inspection of Train A. The remaining portion of the Unit 1 SW system piping will be inspected when Train B is out of service. Any required corrective action will be identified and documented by July, 1986.

SUMMARY

OF EVENTS Date Discovered: December 26, 1985 Date NRC Notified as Potentially Reportable: January 24, 1986 Date Determined Reportable: April 11, 1986 SAFETY IMPLICATION Normally pipe coating failure or corrosion are not considered a safety lisue. The periodic in-service inspection of the class 3 piping would detect any ! ass of integrity of the piping. However, due to the significant erosion-corrosion associated with the cavitation across valve 1SW-023 and rapid loss of integrity of the piping, these deficiencies should be considered as reportable, pursuant to 10CFR50.55(e).

.- Log # TXX-4963 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY

. August 22, 1986

.*3taOff.Y.?!.h Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 INSTALLATION OF SUPER HILTI KWIK BOLTS SDAR: CP-86-08 (INTERIM REPORT)

~.' ear Mr. Johnson:

On February 6,1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the control of stamps used to identify Super Hilti Kwik Bol ts. This is an interim report of a potentially. reportable item under the provisions of 10CFR50.55(e). We have~ submitted interim reports logged TXX-4728, TXX-4773, and TXX-4879, dated March 7, 1986, April 24, 1986, and June 27, 1986, respectively. We received an extension from your Mr. T. Westerman until August 22, 1986.

Field inspections have identified pipe support installations affected by this issue and provided documentation by Nonconformance Reports (NCR's). These NCR's have been evaluated by Engineering and determined to be acceptable "as is".

The scope of the original issue involved ASME pipe support installations. The generic implications of this . issue (non-ASME applications such as cable tray hangers, structural steel, conduit supports, and electrical' equipment installations) are currently being investigated by TUGC0 in response to TUGC0 Corrective Action Report ~(CAR) No. 074.

We are continuing our evaluation and anticipate submitting our next report by December 1, 1986.

Very truly yours,

[I/

W. G. nsil -

By:

G.S. K~eeley Q Manager, Nucleag Licensing JCH/amb

Log # TXX-5044 File # 10010 908.1 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTIE 01JVE STREET. L.B. 81. DALLAS. TEXA8 75301 September 26, 1986 E'IM^JAf?Ja'.'A Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76J12

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ELECTRICAL PENETRATION ASSEMBLIES SDAR: CP-86-10 (INTERIM REPORT)

Dear Mr. Johnson:

On April 24, 1986, we notified you of a reportable item involving the electrical penetration assemblies (EPA's) supplied by Bunker Ramo .

(see TXX-4774). This is a follow-up interim report on a reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4929, dated July 22, 1986.

The EPA modules supplied by Bunker Ramo will be replaced by modules supplied by Conax. Rework in Unit 1 is scheduled to commence by October 27, 1986, and be completed by May 25, 1987. The schedule for the Unit 2 rework has not yet been established. The information will be reported at a later date.

We anticipate submitting our next report by March 27, 1987.

Very truly yours, W

W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A DEVISION OF TEXAS U111Z11ES ELECTR1C COMPANY

Log # TXX-5007 File # 10110 903.7 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER e 400 NORTM 01JVE STREET. L.B. SS . DAIJ.AS. TEXAS 78301 September 12, 1986 J!Put??.f.7.5 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 COMMODITY INSTALLATION AT SECONDARY WALL DESIGN GAPS SDAR: CP-86-12 (INTERIM REPORT)

Dear Mr. Johnson:

On February 27, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving attachments at, or in close proximity to, design gaps between secondary walls and adjacent walls / floors. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). Our last interim report was logged TXX-4923, dated July 21, 1986.

Evaluation of this issue involves three activities. Initially, the engineering contractors charged with design responsibility for the vcrious installed commodities (i.e. conduits, HVAC, cable tray hangers) will evaluate incorporation of a generic displacement for horizontal and vertical movements.

These displacement values will be further refined by Gibbs & Hill for installations for which the generic value is determined not acceptable. The final activity involved in the evaluation of this deficiency will consist of field verification to identify potentially unacceptable interactions between installations.

The results of these efforts will provide the information required to assess the significance of this issue. All efforts are currently underway except the field verifications scheduled to begin in mid-October 1986. We anticipate submitting our next report by November 24, 1986.

Very truly yours, W

W. G. Counsil JCH/amb A DIY18 EON OF TEXAS UTELETTES ELECTR1C COMPANY

-, Y _ , _ __ . , , . . _ , . . - - . - . - . , _ _ -

Log # TXX-4923 File # 10110 '

903.7 TEXAS UTILITIES GENERATING COMPANT SKYW AY TOWEB . 400 NORTH O1JVE STREET.1 5. S 8

• DAI.LAS. TEX.AS 73301 July 21,.1986 33^1?.f?".".*.S Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Rcgulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 COMMODITY INSTALLATION AT SECONDARY WALL DESIGN GAPS SDAR: CP-86-12 (INTERIM REPORT)

Dear Mr. Johnson':

On February 27, 1986, we verbally notified your Mr. T. F. Westerman of a-deficiency involving attachments at, or in close proximity to, design gaps c.

between secondary walls and adjacent walls / floors. ThisisaninterimreporI of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted interim reports logged TXX-4750, TXX-4832, and TXX-4869, dated March 31, 1986, May 30, 1986, and June 20, 1986, respectively.

We are continuing our evaluation and anticipate submitting our next report by September 12, 1986.

Very ,truly yours, W. G. Counsil JCH/arh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEVISION OF TEXAS (ITTLETIES ELECT 3 TIC COMPANY

_ .- _. . , . . _ . - . . _ _ _ _ _ _ . . _ . . _ _ . _ _ , . _ . _ . . - , _ . . _ . . . . . _ . - . . ~ . . . - . - _ . - . . . _ _ . . . _ . _ _ _ , , . , . _ . . .

Log i TXX-4750 File i 10110

. 903.7 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWEB . ese NORTM OEJVE STREET. L.B. 81. DAIJ.AS. TEXAS 78301 March 31, 1986

.TN%2i?.9?.??.h Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 COMMODITY INSTALLATIONS AT SECONDARY WALL DESIGN GAPS SDAR: CP-86-12

Dear Mr. Johnson:

On February 27, 1986, we verbally notified your Mr. T. Westerman of a deficiency involving attachments at or in close proximity to design gaps between secondary walls and adjacent walls / floors. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). The evaluation of this issue involves the assessment by Gibbs & Hill of all secondary wall gaps to determine relative displacements between secondary walls and the above slab.

We are continuing our evaluation and anticipate completion of our final report by June 5, 1986.

Very truly yours, j v H3}i-W. G. Counsli JCH/.srm c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

[ A Dl%'1510N OF TEXAS UTILETTES ELECTRIC COMPANY

Log # TXX-6032 File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SEYWAY M , em leORT,8 OLIVE STRErf,8.3. 85 . DALLAS. TEXAS 7838 October 20, 1986

.". # #,". h B . U

• i Mr. Eric H.' Johnson, Director Division of Reactor Safety and Projects y U. S. Nuclear Regulatery Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 i

JET IMPINGEMENT LOAD REVIEW SDAR: CP-86-13-(INTERIM REPORT) m

Dear Mr. Johnson:

4-On March 5,1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving a computer entry error which could invalidate portions of the jet impingement load review for high energy piping. This'is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

Our latest interim report, logged TXX-4890, was submitted on July 3,1986.

, As previously noted, we have reviewed all component shape factors whose jet loads were calculated using the PIPSCIN jet load program. There are approximately 15 components remaining to be evaluated for non-conservative jet loads from the originally identified group of 1,353. Completion of this evaluation is currently scheduled for October 31, 1986. All component shape factors evaluated to date have been verified to be acceptable.

At this time, 306 of these 355 components have been reevaluated and found to be acceptable as is. Evaluation of the remaining components with non-conservative jet loads is. scheduled for completion by October 31, 1986.

We are continuing our evaluation and anticipate submitting our next report no 4

later than November 21, 1986.

Very truly yours, W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission i Washington, D.C. 20555 4 smsaw or rum.: vreurins uncrase courwr

. - > . - , - . - . _ _ . _ .--..-,_,m ,,_,..,__.m_-,.__.-#_ .. - --...,,_ -. - ._ _ --,_ ,,,r._.,.-.__ -. . _ , _ - , -7 .,,._m.,

Log # TXX-4833 File # 10110 903.11 TEXAS UTILITIES GENERATING CO.TIPANY AMYW AV Tf 5WER ,400 NfMRTH OLIVT; asTREET. L.R. S & . DALLAN. TEX Am 73208 June 2, 1986

.%It'O&fff.'f.'.5 Mr. Eric~H. Jonnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET N0. 50-445 JET IMPINGEMENT LOAD REVIEW SDAR: CP-86-13 (INTERIM REPORT)

Dear Mr. Johnson:

On March :,, 1986, we verbally notified your Mr. T. F. 'aesterman of a deficiency involving a computer entry error which could invalicate cortions of the jet i.mpingement load review for high energy piping. This is an

-interim report of a patentially reportable item uncer the provisions of 10CFR50.55(e). We have submitted interim reports logaed TXX-4753 and TXX-4807, dated April 4, 1986, and May 16, 1986, respectively.

Site engineering has reviewed all component shape factors whose jet loa 3s were calculated using the PIPSCIN jet load program. This revien has concluded that of the 1353 components evaluated using PIPSCIN, 246 have

" shape factors" less than 1.0. Only 174 components may have non-conservative jet loads. A complete review-of these targets has begun and is scheduled to be completed by June 13, 1986.

We are-continuing our evaluation and ant-icipate submitting-our next report by July 3, 1986.

Very truly yours, ni. /* '

//('l/ 'h(7C7tx ~

W. G. Counsil JCH/grr c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A til%'th80N GDV TEXAN VTil21 TEN ELECTNic' reb.%EYANn'

~

Log # TXX-4753 File # 10110 TEXAS UTILITIES GENERATING COMPANY i SKYWAY TOWEB e 400 NORT,8 OEJVE STREET. L.B. S t

• DALLAS. TEXAS 78201 April 4, 1986

.TW'EO 'U.?Ah Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000

' Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET N0. 50-445 JET IMPINGEMENT LOAD REVIEW SDAR: CP-86-13 ,

~

Dear Mr. Johnson:

On March.5, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving a computer entry error wnich could invalidate the jet impingement load review for high energy piping. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

During the design verification process of the PIPSCIN jet load program, an error was found in the input instructions which produced loads on jet targets that were not applicable. The issue is applicable to Unit 1 only.

Currentl'y, Gibbs & Hill has Deen directed to determine the adequacy of the jet load calculations. Corrective action will be implemented for jet loads determined to be in error.

We are continuing our evaluation and anticipate completion of our final report by May 16, 1986.

Very truly yours, sh'h{Q W. G. Counsil By: ,- 6 /

G. S. Keeley Manager, Licensing thc,hra,rj[

JCH/grr c- NRC Region IV (0 + 1 copy)

Director, inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIVISION OF TEXAS tlTILETIES ELECTRIC COAtPANY

Lig # TXX-6034 Fi e 0 10110 909.5 TEXAS UTILITIES GENERATING COMPANY SEYWAY TOWER e 480 MORT,8 OEJVE STREET. L.S. 83 . DALLAS, TEXAS 783D8 October 20, 1986 "MO h.T.UM, Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 FIRE EFFECTS ON INSTRUMENT TUBING.

SDAR: CP-86-16 (INTERIM REPORT)

Dear Mr. Johnson:

l On' March 21, 1986, we verbally notified your Mr. R. Hall of a deficiency involving the detrimental effects of low melting point metals (zine) on stainless steel instrument tubing during a fire. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our latest interim report, logged TXX-5014, was submitted on September 17, 1986.

The significance of stainless tubing in direct contact with galvanized material (zine) such as Unistrut supports and clamps during a fire is currently being evaluated by Engineering. Field veri.fication efforts to identify galvanized hardware utilized for supporting instruments required for fire safe shutdown have been completed.

A testing program has been developed for the detection of zinc surface contamination of the instrument tubing. The results of this program will allow evaluation of possible deleterious effects of zinc contamination. The testing program and the subsequent evaluation is expected to be completed by l, December 31, 1986.

l We anticipate submitting our next report by January 21, 1987.

j_ Very truly yours, l W. G. Counsil JCH/mlh l

l c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

a omsoon or rxxas enunns u.senne cowaur

.- . - . , _ _ - ~ - - - - - - ,e. - - - a,--,,----a ~,--------------.w---w--,n-ee -mm,--we-~r-,m-.v-,,-,~va----e,---------,---m- me.---- ,ev--e-e---,--,-,-w ----r, e..,-

Log # TXX-5014 File # 10110, 909.5 TEXAS UTILITIES GEhT. RATING COMPAhY SSEYWAY TOWEB . 40e NORTM OEJVE WFRENT. L.B. S 8 . DAILAS. TEXAS 75901 September 17, 1986

,*'.W'E *i.*NE.*.%

Mr. Eric'H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive,- Suite 1000

- Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 FIRE EFFECTS ON INSTRUMENT TUBING SDAR: CP-85-16 (INTERIM REPORT)

Dear Mr. Johnson:

On March 21, 1986, we verbally notified your Mr. R. Hall of a deficiency involving the detrimental effects of low melting point metals on stainless i steel instrument tubing during a fire. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). On September 5,1986, we verbally requested and received an extension for submitting this report from your Mr..I. Barnes until September 17, 1986. We have submitted interim reports logged TXX-4767 and TXX-4842, dated April 21, 1986, and June 6, 1986.respectively.

The significance of stainless tubing in direct contact with galvanized material (zine) such as Unistrut supports and clamps during a fire is being evaluated by Engineering. The complexity of the interaction and the probability and duration of a simultaneous occurrence of high tensile forces in the presence of molten zinc at temperatures above 7500C are being considered.

l A field verification has been completed to identify all galvanized hardware utilized for supporting instruments required for fire safe shutdown. It is anticipated that the evaluation will be completed by September 30, 1986. The schedule for any resulting corrective measures and the reportability of that item will be established at that time.

We are continuing our evaluation of this issue and anticipate submitting our next report by October 22, 1986.

Very truly yours, l W. G. Co s1 i

i By: < .

G. S. Keeley w /

Manager, Licensing}

JCH/amb , ,,,,,,,,, c, ,,,, gram,, ,,,,cr,,c co,,,,,

_,.-.,,r., m,_-___ -.._.. , - _ _ . , . _ _ _ , , - --

, ,-_,_.,__,w_ _ . . . . _ . _ , _ , - , , . -_ _ _ _ _ _ , _ _ _ , , , _ _ _ _ , . , - . .

Log # TXX-5027 File # 10110 909.4 TEXAS UTILITIES GENERATING COMPANY

, SKYWAY TOWER . 400 NORTH OLIVE STREET. L.B. en . DALLAS. TEXA5 75208 September 19, 1986 anWi*f.f.7.it Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SAFETY CHILLED WATER CHILLER UNITS SDAR: CP-86-18 (SUPPLEMENTAL REPORT) ,

Dear Mr. Johnson:

On May.21, 1986, we notified you that the issue involving difficulties in starting and operating the safety chilled water chiller units was reportable under the provisions of 10CFR50.55(e). We have submitted supplemental reports logged TXX-4875 and TXX-4934, dated June 26, 1986, and July 24, 1986, respectively.

Currently, the cognizant engineering contractor, Gibbs & Hill is performing a detailed review of vendor specifications and updating the list of components serviced by the component cooling water system. The supplier (York) has indicated the installation of chiller flcw control valves will resolve deficiencies with an operating safety chiller, but.an evaluation is required (and underway) to review this modification with regards to a standby, non-operating safety chiller which must start during an accident scenario.

Westinghouse is being contracted to evaluate the impact of the 400F CCW temperature on'NSSS components. Our final conclusions concerning this issue l

will be based upon receipt of the information from these vendors.

We are continuing our' evaluation and anticipate submitting our next report by December 17, 1986.

i Very truly_yours, l

W. G. Cou 1 By: -

G. S. Keeley 7/A/ '/ ~

Manager, Licensin JCH/aeb A DEVISION OF TEXAS UTTLIETES ELECTRIC COMPANY t . . -.

Leg # TXX-5045 File # 10010 S10.3 TEXAS UTILITIES GENERATING COMPANY SETWAY TOTER . 449 NOSTM OE.2VE STREET. L.B. 84 . DALLAS. TEXAS 78991 September 26, 1986-

,* "l";;*":.*.;

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission ,

611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) '

DOCKET NO3. 50-445 AND 50-446 PRESSURE INSTRUMENT INSTALLATIONS SDAR: CP-86-19 (INTERIM REPORT)

Dear Mr. Johnson:

On March 21, 1986, we notified you of a reportable item involving the installation of steam service pressure transmitters (see TXX-4824). This is a follow-up interim report to status the corrective actions for a reportable item'under the provisions of 10CFR50.55(e).

As specified in the previous response, engineering has evaluated all Unit 1 and 2 steam service installations to identify additional instruments which are mounted above their root valves without wet legs. During the redesign process

, for the pressure instruments mounted above the steam line root valves, an additional concern was encountered which affects this effort.

This additional concern involves a potential change in the criteria for layout and/or support design due to post-accident elevated temperatures which may affect the tubing for these main steam instruments. An integrated design approach which will address both concerns is being pursued.

We anticipate submitting our next report on this issue no later than January

21, 1987.

Very truly yours, I

(f??b W. G. Counsil l JCH/amb c - NRC Region IV (0 + 1 copy) i Director, Inspection and Enforcement (15 copies) >

, U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l

l 4 myrssou or 7xxas ustrarxxs armernic couraur I

I._-- . -_._.- _ __ _ -.-_ __ _. _ , -

Log # TXX-4994

• File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTH 08JVE Ff1EET. L.B. S 8

• DALLAS, TEXAS 7S30 8 September 5, 1986 c

Ch?L*a ?.l.7.2 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012 ,

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 QUALIFICATION OF RAYCHEM KIT NPKS-02-01 SDAR: CP-86-21 (INTERIM REPORT)

Dear Mr. Johnson:

On March 24, 1986, we verbally notified your Mr. T.F. Westerman of a deficiency involving possible discrepancies in vendor (Raychem) methodology for testing of environmental qualification which may render the Raychem Kit NPKS-02-01 unacceptable for specific published applications. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted interim reports logged TXX-4772, TXX-4830, and TXX-4913, dated April 23, 1985, May 28, 1986, and July 16, 1986, respectively.

The specific deficiency involves a heat shrink kit used for in-line butt-splices. The kit consists of two inner sleeves which are enclosed by an outer sleeve. When overlapped at the butt-splice, the effective outside diameter of the inner sleeves is greater than the specified useful range of the outer sleeve. Raychem has indicated the condition is the result of an earlier design deficiency in which the American Wire Gauge (AWG) standard was used to size the outer sleeves as opposed to specifying a kit-specific outside diameter.

Discussions with the supplier indicate the Raychem design deficiency has been corrected and CPSES applications of the kit have been specifically qualified.

Receipt and review of reporting documentation is scheduled for completion on September 5, 1986.

We are continuing our evaluation and anticipate submitting our next report by September 26, 1986.

Very truly yours, W. G. Counsil dCH/amb a omssou or rexas ununes etecrmc couraur

Log # TXX-5008 File # 10110 909.4 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NOSTM OLIVE WTREET. L.M. 81. DALLAS, TEXAS 75501 Sep,tember 12,.1986 epa *Lc? .7.ib Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 SAFEGUARDS AREA FAN COOLERS SDAR: CP-86-22 (INTERIM REPORT)

Dear Mr. Johnson:

On April 2,1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the capacity of the present fan cooler design in the Safeguards area to adequately handle the heat load in several rooms. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted interim reports logged TXX-4780 and TXX-4894, dated April 30, 1986, and July 3, 1986, respectively.

Since our last report, we have initiated a major review of the HVAC design by EBASCO. This design review will include resolution of this specific issue and a determination of reportability pursuant to 10CFR50.55(e).

We anticipate submitting our next report by December 12, 1986.

Very truly yours, 4

W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

' Director, Inspection & Enforcement (15' copies)

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 .

A DIY1980N OF 1EKAS U1112 TIES ELECTEIC COMPANY

Log # TXX-6025 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SKYWAY ttMFEE . ese MORTH olive STREET.1.B. el . DALLAS. TEXAS 78sp8 October 17, 1986 E'#1".Lff.Unb Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 STIFFNESS VALUES FOR CLASS 1 STRESS ANALYSIS SDAR: CP-86-33 (FINAL REPORT)

Dear Mr. Johnson:

On April 29, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the use of incorrect pipe support stiffness values in the Unit 1 Class 1 pipe stress analyses. We have submitted interim reports logged TXX-4831 and TXX-4976, dated May 28, 1986, and August 22, 1986, respectively.

We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.

DESCRIPTION As identified during the CPSES pipe support requalification effort, incorrect stiffness values were used in the Unit 1 Class 1 piping stress analyses.

Review of the ongoing requalification prograta has indicated that approximately 30% of the existing pipe supports are overstressed or require modification primarily due to load increases. The factors contributing to increased support loads include support optimization, revised damping values, trapeze modifications, and possibly stiffness.

As a result of these conditions, all stress problems are currently scheduled for reanalysis. The recalculation of a stress analysis to specifically isolate the effects of stiffness or any other attribute would require multiple iterations. These iterations are costly and unproductive, and therefore will not be performed.

SAFETY IMPLICATIONS In the event the deficiency had remained undetected, the integrity of the Class 1 piping and supports could not be assured during normal operating or accident conditions.

A DEVl500N OF TEXA5 L71LITIES ELECTRIC COMPANY

+ -s TXX-6025 ,

October 17, 1986 l Page 2 CORRECTIVE ACI1QN This evaluation is continuing and support modifications will be issued as required to alleviate all unacceptable conditions. The status of support-modifications is being reported under 10CFR50.55(e) via SDARs CP-86-36, CP 63, and CP-86-72.

Very truly yours,

@4 W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i

l-4

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Log # TXX-4976 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANT SKYW AY TOWER . 400 NORTM OLIVE STREET. L.B. e a a D ALLAS. TEXAS 78301 -

August 22, 1986 E M' :a?? ,".ib Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 STIFFNESS VALUES FOR CLASS 1 STRESS ANALYSIS SDAR: CP-86-33-(INTERIM REPORT)

Dear Mr. Johnson:

On April 29, 1986, we verbally notified your Mr. T.F. Westerman of a deficiency involving the use of incorrect pipe support stiffness values in the Unit 1 Class 1 pipe stress analysis. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4831, dated May 28, 1986.

A reanalysis of all Class 1 stress problems in Unit I has been completed. No piping over-stresses were encountered due to support stiffness changes. The final evaluation of the effect of stiffness changes on valves,' components, local stresses, penetrations, Reactor Coolant Loop nozzles, fatigue, and break locations is currently in progress. Stone & Webster Engineering Corporation (SWEC) is currently evaluating supports for the new loads resulting from the reanalysis.

l We are continuing our evaluation and anticipate submitting our next report by October 17, 1986.

Very truly yours, bU n,5b W. G. Counsil By: . lW/

G.S. Keeley , /,

Manager, Nucleary.t.icensing JCH/amb l

t

Log # TXX-4831 File # 10110 TEXAS UTILITIES GENERATING COMPANT 903.9 B BCYW AY TOWEB .400 9805T3. OIJVE INTREET. L B. S S

• DALLAS. TEXA5 7830 8 w m i May 28, 1986

. . .a..u... . .o..c.o..u...s. c Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NO. 50-445 STIFFNESS VALUES FOR CLASS 1 STRESS ANALYSIS "

SDAR: CP-86-33 (INTERIM REPORT)

Dear Mr. Jonnson:

On April 29, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the use of incorrect pipe support stiffness values in the Unit 1 Class 1 pipe stress analysis. Tnis is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

Stone & Webster Engineering Corporation (SWEC) has completed the calculations of all stiffness values for the pipe supports on Class I stress problems. Westinghouse is reanalyzing these stress problems and issuing revised pipe support loads to SWEC for review. No piping overstress situations have been encountered for the stress problems where loads have been issued. SWEC has not yet started to assess the existing supports for adequacy due to load increases.

We are continuing our evaluation and anticipate submitting our next report by August 22, 1986.

Very truly yours,

.Y W. G. Counsil JCH/grr c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEVISION OF TEXAR UTIL2T8ES ELECTRIC COAtPANY

Log # .AX-5009

. File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY rwar row . no.1= ouv= .r===r, a .. .. . ouu.. T=XA. M304 Septe.mber 12, 1986 ei.NTONE:.*.h Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 MOTOR OPERATORS FOR MANUAL VALVES SDAR: CP-86-35 (INTERIM REPORT)

Dear Mr.. Johnson:

On June 2,1986, we verbally notified you of a reportable item involving the motor operators for several valves in the main steam system (see TXX-4840).

We have submitted an interim report logged TXX-4924, dated July 21, 1986.

As noted in our previous response, two corrective action avenues were under consideration. We have elected to implement the option of replacing the valves with fully qualified valves. Design activities are currently scheduled for completion by April, 1987.

We anticipate submitting our next report May 15, 1987.

Very truly yours, SVA W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 ,

l.

l l

l i

i A orvssson or1sxAs trsitzrtzs eszernsc courANY l

l

Log # TXX-6044 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY esvw v ww m . = ouve er===r. i . -m - nx non October 17, 1986 i

e aC five ce re s  ?

J Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000

Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)-

DOCKET NOS. 50-445 AND 50-446 i LARGE BORE PIPING AND SUPPORTS SDAR: CP-86-36 (INTERIM REPORT) 3

Dear Mr. Johnson:

On June 9, 1986, we notified you of a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification

, program (see TXX-4844). This is a follow-up interim report on a reportable item under the provision of 10CFR50.55(e). We have submitted interim reports i logged TXX-4958 and TXX-5033, dated August 13, 1986, and September 26, 1986, respectively.

In order to provide more accurate results and scheduling information, the

, scope of this issue has been revised to delete small bore (2" and less) ASME Class 2 and 3 piping and supports that are not part of the large bore or Class

1 stress problems. An additional reportable ites - identified as SDAR CP 72, Small Bore Piping and Supports - has been issued to encompass these scope i deletions (see TXX-6042).

i The continuing engineering evaluation for large bore piping and supports has identified the following additional instances which are considered reportable pursuant to 10CFR50.55(e). These instances are within modification category 4

" Cumulative Effects" and are further defined as follows:

1. Fluid Transients:

, Original design activities considered the effects of fluid transients in only three systems. During the requalification

! program, additional systems have been identified and analyzed wherein the effects of fluid transients have resulted in increased pipe support loads. Modifications of these supports will be l required.

i

2. Support Stability:

Original design requirements for specific support types did not l include adequate provisions to assure support stability.

Specifically, measures were not provided to preclude axial movement or rotation of the piping to an " unqualified position". An

" unqualified position" results from movement or drifting of the support to a position other than that assumed in the piping stress analysis.

4 omsaw or m4: enunas sucrar comemur

J -

TXX-6044 October 17, 1986 '

Page 2 of 2 4 Specific support types affected by this condition include:

a) "Zero" clearance box frames supported by struts,

, b) long column-strut supports, and

' c) U-bolts on single struts or snubbers exhibiting overstress.

3. General Cumulative Effects:

During the requalification program, all stress problems and supports have been scheduled for re-analysis and evaluation. Pipe support modifications have been required as a result of the cumulative effects of the multiple design issues. Multiple iterations would be required to isolate the effects of any specific design attribute.

These iterations are costly and therefore will not be performed.-

Specific issues contributing to these cumulative effects can be categorized as follows.

a) Generic stiffness b) Axial rotational restraints.

c) Support mass d) Mass point spacing

. e) High frequency mass participation f) Fluid transients g) Support load increases due to support optimization.

l The attached list shows the support modifications initiated to date. The evaluation of this issue is continuing. We anticipate submitting our next report by December 1, 1986.

Very truly yours, I

W. G. Counsil I

JCH/amb

! Attachment

,- i c - NRC Region IV (0 + 1 copy) i Director, Inspection & Enforcement (15 copies)

! U. S. Nuclear Regulatory Commission I Washington, D.C. 20555

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-s

• TXX-6044

, October 17, 1986 Page 1 of 1 ATTACHMENT LARGE BORE PIPE SUPPORT M00!FICATIONS Number of Small Bore 11011 Cateaory Modifications Deletions

• 1 Prudent 865 26 Recent Industry Practice 1041 56 Adjustinent 97 33 Cumulative Effects 470 32 2 Prudent 1272 4 Recent Industry Practice 253 14.

Adjustment 90 10 Cumulative Effects '

328 74

• These modification quantities have been subtracted from earlier report totals as a result of the revised scope of-this SDAR. These small' bore modifications quantities will now be reported and updated in SDAR CP-86a72.'.' .

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Log # TXX-5033 File # 10010 903.9 TEXAS UTILITIES GENERATING COMPANY SEYWAY TOWWA . 400 NORTag OLIVE STREET. L.B. 8 8

• DALLAS. TEXA5 75301 September 26, 1986

.").T7Af?Jt!.S Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012 -

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 PIPE SUPPORTS SDAR: CP-86-36 (INTERIM REPORT)

Dear Mr. Johnson:

On June 9,1986, we notified you of a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program (see TXX-4844). This is a follow-up interim report on a reportable item under the provision of 10CFR50.55(e). We have submitted an interim

• report logged TXX-4958, dated August 13, 1986.

The continuing engineering evaluation has not identified any additional instances which are considered reportable pursuant to 10CFR50.55(e). The attached list shows the support modifications initiated to date. The evaluation of this issue is continuing and we anticipate submitting our next report by October 29, 1986.

Very truly yours, W. G. Counsil JCH/amb Attachment c - NRC Region IV (0 + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A DIVISION OF TEXAR UTTLETIES ELECTRIC COMPANY

~ ...

ATTACHMENT PIPE SUPPORT MODIFICATIONS Number of Mn11 Cateaory Modifications

~I Prudent 762*

Recent Industry Practice 921 Adjustment 56 Cumulative Effects 237 II Prudent 1265 Recent Industry Practice 209 Adjustment 63 Cumulative Effects 319 The reduction in this category from the previous report represents Trapeze supports that were previously identified for modification, and were subsequently deleted; thits were recategorized in "Recent Industry Practice".

i l

h i

l

' File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANT SKYW AY TowBa ,400 NORTM OLnt STREET, L.B. S & = DALLAS. TE3LAs Tsag g August 13, 1986

.7.'M" Aff.f.?.'.'I, Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012 ,

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 PIPE SUPPORTS .

SDAR: CP-86-36 (INTERIM REPORT)

Dear Mr. Johnson:

On June 9, 1986, we notified you of a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program (see TXX-4844). This is a follow-up interim report on a reportable item under the provisions of 10CFR50.55(e).

The continuing engineering evaluation has not identified any additional instances which are considered reportable pursuant to 10CFR50.55(e). The attached list shows the support modifications initiated to date. The evaluation of this issue is continuing and we anticipate submitting our next report by September 26, 1986.

Very truly yours, 0.c,. Q W. G. Counsil By:

D. R. Woodlan Licensing Supervisor JCH/arh Attachment c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIVl510N OF TEX AN LTELETIEM ELECTRIC COMPANY

ATTACHMENT PIPE SUPPORT MODIFICATIONS Unit Cateaory , Number af Modifications

• Im Prudent 852 Recent Industry Practice 364 Adjustment' 2 Cumulative Effects 83 II Prudent 691 Recent Industry Practice ,

90 Adjustment 22 Cumulative Effects 144

• Changes in these figures from the last report represent not only identification of further modifications but a reclassification and recategorization of certain supports.

903.9 TEXAS UTILITIES GENERATING COMPA.W v ,w.... aouv. ==.r.u.....o u ..v. .. .

June 9, 1986 anTL*,?.if.7.W.

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 PIPE SUPPORTS SDAR: CP-85-36 (INTERIM REPORT)

Dear Mr. Johnson:

On May 9,1986, we verbally notified your Mr. I. Barnes that the scope of plant modifications resulting from the project's pipe support reverification program could be considered potentially reportable under the provisions of 10CFR50.55(e). The engineering evaluation to date has identified one instance which is reportable under the provisions of 10CFR50.55(e). The evaluation of this issue is continuing and we anticipate submitting our next report by August 13, 1986.

Very truly yours,

$b n.Ch W. G. Co sil By: /

G. 5. Keel Manager, Nu icensing JCH/arh Attachment c - NRC Region IV (0 + 1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A t)fVISION or 7:' TILIT8Cs ELECTRIC CUMPANt'

ATTACHMENT

, PIPE SUDPORTS DESCRIPTION The issue involves the project's pipe support reverification program being conducted by Stone and Webster Engineering Corporation (SWEC). This program employs an expanded set of design and installation criteria for tne evaluation of the structural adequacy of existing installations.

While the primary scope of SWEC's work is to provide technical verifications, modification of certain pipe supports will provide expedient acceotance for the expanded requirements. Initial results indicate support modifications are categorized as follows:

1. Prudent. Acceptance by physical modification versus analysis. Supports in this category may be technically acceptable; however, more time and expense would be involved than that required to physically modify the support and qualify the modification.

2. Recent NRC and Industry recommended practice. Modifications implemented to eliminate snubbers to enhance plant maintainability, reduce in-service inspection, and minimize wor.ker, exposure (operating plant conditions).

3. Adjustment. Minor modifications (such as re-torquing or shimming) implemented to meet more rigorous installation criteria contained in the resolution of the external source technical issues.

4. Cumulative effects. Modifications that may be required due to the combined effect of multiple issues.

The scope of plant modifications resulting from this reverification program is of a magnitude such that it was considered potentially reportable under the provisions of 10CFR50.55(e).

The issue is applicable to Units I and 2 and involves all, safety class piping systems.

The engineering evaluation to date has identified one instance which is reportable. On the seismic evaluation of stress problem 1-045T, for the chemical volume and control system (CVCS), the SWEC requalification has indicated an overstress condition. The cause for the condition was the use of inappropriate response spectra in the previous Gibbs and Hill piping analysis.

SUMMARY

OF EVENTS Date NRC Notified as Fotentially Reportable: May 9, 1986.

Date Determined Reportable: June 9, 1986.

SAFETY IMPLICATION The overstress condition in the CVCS, stress problem 1045T, were it to have remained uncorrected, could have adversely affected the safety of operation of the plant in the event of an earthquake.

AIIALHPtNT

, PIPE SUPPORTS continggd COPRECTIVE ACTION Corrective action is to add sufficient additional supports to relieve the overstress problem. Appropriate spectra will continue to be used for all stress problems in the requalification program, as was being used when the condition was identified.

In addition to the above, the support modifications initiated to date, by

, category as listed in the description section of this report, are as follows.

Unit Catacory Nutbar of Modifications I Prudent 992 Recent Industry Practice 177 Adjustment 0 Cumalative Effects 15 II Prudent 699 Recent Industry Practice 35 Adjustment 11 Cumulative Effects 0

^

Subsequent status reports will continue to update the above list, and add additional support modifications which may be identified and initiated.

We anticipate submitting our next report no late than August 13, 1986.

Log # TXX-5010 File # 10110 908.3 TEXAS UTILITIES GENERATING COMPetNT v.4, -.. . no.r ouv. ar===r. o. .. . . . 4u .. MRA. M. ,

Sep.tember 12, 1986 53%7A.*f.ffYA Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commissicn 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 TRACEA8ILITY OF IE PIGTAIL EXTENSIONS SDAR: CP-86-38 (INTERIM REPORT)

Dear Mr. Johnson:

On May 27, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the failure of project procedures to adequately address the installation and inspection criteria for cable runs used as device pigtail extensions. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted interim reports logged TXX-4873 and TXX-4925, dated June 26, 1985, and July 21, 1986, respectively.

The analysis noted in our previous response to determine the impact of the lack of traceability of pigtail extensions has been concluded by Gibbs & Hill.

Currently, field verifications are scheduled to begin in mid-October 1985 to identify the location of existing pigtail extensions. Using this as-built data, an evaluation will be performed to review the specific significance of this issue.

We are continuing our evaluation and anticipate submitting our next report by December 17, 1986.

Very truly yours,

$ WH W. G. Counsil JCH/amb ,

c - NRC Region IV (0+ 1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A 8)lVihiUN or TEXAN L*ttLETit5 ELEC7Nie1 CUAtPANt*

+

Log # TXX-4925 File # 10110 908.3 TEXAS UTILITIES GENERATING COMPANY m vvo .. ..r,.ouv. ..r.c.....ouu..,.u.....

July 21, 1985 Jnba" * *?.f.".S Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 011 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 TRACEABILITY OF IE PIGTAIL EXTENSIONS SDAR: CP-86-38 (INTERIM REPORT)

Dear Mr. Johnson:

On May 27, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the failure of project procedures to adequately address the installation and inspection criteria for cable runs used as device pigtail f.

extensions. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted an interim report logged TXX-4873, dated June 26, 1986.

We are continuing our evaluation and anticipate submitting our next report by September 12, 1986.

Very truly yours, s ]

/ff d'A' W. G. Counsil JCH/arh c-NRCRegionIV(0+1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIY1580N 09' TEXAN t?T112TtEN ELECTxic COMPANY

. _ ~ _ _ . - ---- . - . --_ ,,,- - _ - - _- -__ . _ . _ -

File # 10110 908.3 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWEB . 480 NOST98 OLJVE STREET. L.D. e 8 . DALLAS. TEXAh TSSO R June 25, 1986

n2:&?.9?.1.2, Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 TRACEABILITY OF IE PIGTAIL EXTENSIONS SDAR: CP-86-38 (INTERIM REPORT)

Dear Mr. Johnson:

On May 27, 1986, we verbally notified your Mr. T. F. Wester.1an of a deficiency involving the failure of project procedures to adequately address the installation and inspection criteria for cable runs used as device pigtail extensions. .This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e).

CPSES Engineering is currently conducting an analysis of this issue to evaluate the impact of the lack of traceability of pigtail extensions by cable number.

We are continuing our evaluation and anticipate submitting our next report by July 21,1986.

Very truly yours, h'. 7td $

M G. S. Keeley Manager, Nucle icensing JCH/arh c - NRC Region IV (0 + 1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 4 orvissnv or raxas urrurres marcrase cmsra.vr

~

N Log # TXX-6056 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NOST98 OtJVE STREET. L.m. 8 8 . DALLAS. TEXAS 7890 3 October 21, 1986

1. 3^JA??JnD Mr. Eric H. Johnson, Director Division cf Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 CABLE TRAY C-TYPE CLAMP AND DIMENSIONS SDAR: CP-86-39 (INTERIM REPORT)

Dear Mr. Johnson:

On May 27, 1986, we verbally notified your Mr. T. F. Westerman of a deficier.cy involving dimensional tolerances of the shims used in conjunction with C-Type clamps on cable trays. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted an interim report logged TXX-4874, dated June 26, 1986.

Original design requirements specified shim plates when utilized with "C" type clamps to be flush with the tray web and extend a maximum of 1/2" beyond the outside of the web. This requirement provides shimming under the full width of the tray flange. .

Due to an error in transferring information from the original design change to the erection and inspection drawing, the shim plate was given a tolerance of plus or minus 1/2" from the tray web. This allowed the shim plate to be installed up to 1/2" inward from the web underneath the tray flange. As a result, some unacceptable clamp / shim configurations could have been installed and accepted.

To address this issue, a study has been conducted which indicates that local stresses in the tray flange near the "C" clamp, due to the maximum anticipated loading conditions, are less than the allowable plastic limits given in the CPSES FSAR except for the T. J. Cope 4" x 12" tray section. Further evaluations are required for the T. J. Cope 4" x 12" tray to establish the correlation between the limiting acceptable seismic "g" values and the

, expected specific response accelerations. The limiting seismic accelerations of concern are in the direction perpendicular to the tray plan, i. e. for the horizontal trays, it is in the direction of the natural gravity - downward.

A testing program has been initiated to evaluate the T. J. Cope 4" x 12" tray / clamp configuration. It is anticipated that this testing will be complete by November, 1986.

A DEV1SION OF TEKA8 E171LETTE9 ELECTERC COMPANY

k.

-TXX-6056

~0ct:ber 21, 1986 Page 2 of 2 Our final evaluation will be performed upon completion of testing. Based on the schedule projected For these activities, we anticipate submitting our next report by November 28, 1996.

yours Very5tr1 60 6 4, W. G. Coun i By: . ,/ '

G.S. Keeley - L Manager, Nuclear Licengng JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcemant (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 i

I

F1Te' ( 10110 903.9 TEXAS UTILITIES GENERATING COMPANY v.., w . . no.= ouv. .r .v. i_.. . . nau .. nsa. n .

- June 26, 1986

.*'hifib*30.51 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000

~ Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446~

CABLE TRAY C-TYPE CLAMP SHIM DIMENSIONS SDAR: CP-86-39 (INTERIM REPORT)

Dear Mr. Johnson:

On May 27, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving dimensional tolerances for the shims used in conjunction with C-Type clamps on cable trays. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e).

This issue is related to CP-85-19, Conduit Support Spans, and CP-85-34, Conduit Support Design, and these issues are being evaluated under CPRT Program Item VIII. All electrical raceway items (tray, conduit, supports) have been consolidated under the scope of Ebasco Services. This program plan is scheduled for completion in September,1986. We are continuing our evaluation and anticipate submitting our next report by October 21, 1986.

't Very truly yours,

//[.l Su@

/

G. S. Keeley /

Manager, Nuc Wer L sing l

i JCH/arh l

l c - NRC Region IV (0 + 1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 l

A DEVESION 07 TEXA8 i:TTLETTES ELECTRIC CU%fPA % '

I Log # TXX-6062 File # 10110 915.6 TEXAS UTILITIES GENERATING COMPANY

• WEYWAY TOWER 4AD NORT,8 OLIVE STREET. L.B. 88 e DAM TEXAS 78398 October 29, 1986

,.'Ne'$?. L.'?.Eik Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Comission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SMALL BREAK LOCA MODE 4 OPERATIONS SDAR: CP-86-41 (INTERIM REPORT)

Dear Mr. Johnson:

On May 28, 1986, we verbally notified your Mr. I. Barnes of a deficiency --

involving small break LOCA evaluations regarding the effects of the operational status of plant equipment during Mode 4 operations. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted interim reports logged TXX-4876 and TXX-4959, dated June 26, 1986, and August 13, 1986, respectively.

The Westinghouse Owners Group, of which TUGC0 is a member, accepted a program designed by the WOG Analysis Subcomittee to address this concern at their l September, 1986 meeting. The projected schedule outlines an April, 1987 completion ~date.- Allowing for a reasonable delay time in distributing the -

, conclusions ~from the subcomittee to all affected parties, we anticipate l submitting our next report on this issue by June 12, 1987.

2 1- Very truly yours, ,

C W. G. Counsil JCH/mlh c - NRC Region IV (0 + 1 copy) f i Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Comission

Washington, D.C. 20555 l

l A NYISf0N OF TEXAS LTILFTIES ELECTRIC COMPANY

_ . - . . ~ _ _ . _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ . .-

Log # TXX-4993 4 File # 10110 l 908.3 TEXAS UTILITIES GENERATING COMPANY meIYWAY TOWB3. des NORT38 OtJVE WFREET. L.B. e a . DALLAS. TEXAS 75904 ji September 2, 1986 02*: ?eNE.7.*.K Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 I&C CABINET POWER SUPPLY BREAKERS SDAR: CP-86-42 (FINAL REPORT)

Dear Mr. Johnson:

On June 4,1986, we verbally notified your Mr. I. Barnes of a deficiency involving Class IE I&C cabinet power supply breakers. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

We have submitted interim reports logged TXX-4886 and TXX-4945, dated June 27, 1986, and July 30, 1986, respectively.

Various Class IE I&C cabinets had a deficiency where a fault in one DC power supply could cause the common feeder to trip resulting in the loss of both DC power supplies. However, the control function would still be maintained through the redundant train 80P or NSSS 7300 analog cabinets. Therefore, this is not a significant deficiency in the final equipment design and there is no breakdown in the QA Program. However, the panel board circuit breaker rating was increased to ensure proper coordination with the power supply circuit breaker. This ' corrective action did not require any major change in design, extensive evaluation, or significant rework.- No adverse conditions exist.

l The issue is not reportable under the provisions of 10CFR50.55(e). Records i supporting this determination are available for your inspectors to review at the CPSES site.

Very truly yours,

~

M !k W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIVinl0N OF TEXAS UTTLITIES ELECTRIC COMPANY

Log # TXX-6035

, File 4 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SEYWAY M . 4es asceTM OLIVB WTREET. L18, . DA1AAa. TEXAS 7938 October 20, 1986 Uscu e s ce  ?

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 -

WELDED ATTACHMENTS TO EMBED 0ED STRIP PLATES - ~

SDAR: CP-86-44 (INTERIM REPORT) y

Dear ,

Mr. Johnson:__ _ , , , _ , ,

On June 5,1986,' we verbally notified your Mr. I. Barnes of a deficiency l involving the design / construction requirements for minimum separation of welded attachments to embedded strip plates which were not- properly reflected in inspection procedures. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted .

interim reports logged TXX-4892 and TXX-4978, dated July 3,1986, and August

!. 22, 1986, respectively.

During the course of this evaluation one additional related concern was noted.

Existing quality control instructions did not delineate criteria for the separation between loaded embedded plates and Hilti anchor bolts. Therefore, the scope of this evaluation has been expanded to encompass this issue.

To prevent recurrence of this condition, the following action has been formulated. Specification 2323-SS-30, " Structural Embedments," has been revised and Civil Engineering's instruction CEI-20 is being revised to clarify concrete anchor spacing criteria. Construction procedure CCP-45, " Permanent and Temporary Attachments to Embedded Wald Plates," has been revised to clarify installation criteria and construction attributes. Quality Control Procedure QI-QP-II.14-13, " Separation Verification of Attachments to Loaded

. Embedded Plates," has been developed to address the inspection of attachments

,to embedded plates and spacing requirements for welded attachments,. loaded Hilti'boits, and Richmond inserts. This procedure will also address the inspection of previous and in-process installations.

Due to the revised scope of this issue, the identification (through field verification and subsequent evaluation) of installations in Unit 1 involving the spacing of anchors / attachments is scheduled for completion by January 16, 1987. In Unit 2, the Wall Embedments and Beams (WEB) program will provide identification and analysis of all embedded plate attachments. A plan for the reinspection of existing Unit 2. embedded plate attachments is in development.

A St,1 SON OF TEXAS LTILJTIES ELEC728C NANY

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" ^* TXX-6035

, ,, October 20, 1986 Page 2 We anticipate submitting our next report by February 6, 1987.  !

Very truly yours, W. G. Counsil JCH/mlh-c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission , .. . ,

Washington, D.C. 20555 ,

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Log # TXX-4978 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY r . .=vw4r vo-=. . m ouva n ===r. i .. .. . mu .. nu. ,....

August 22, 1986 EMC?d?A2!,

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 i Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 WELDED ATTACHMENTS TO EMBEDDED STRIP PLATES SDAR: CP-86-44 (INTERIM REPORT)

Dear Mr. Johnson:

On June 5,1986, we verbally notified your Mr. I. Barnes of a deficiency involving the design / construction requirements for minimum separation of welded attachments to embedded strip plates not being properly reflected in inspection procedures. This is an interim report of a potentially. reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4892, dated July 3,1986.

A preliminary evaluation has been conducted in Unit 1 by Engineering to determine the approximate scope of embedded plate welded attachment spacing violations. It was determined out of approximately 800 embedded plate attachments,113 violations exist. TUGC0 QC will perform a backfit inspection to determine the as-built condition on all embedded plates for Unit 1. The inspection results will identify and document all embedded plates with attachment violations. The Structural Embedment Group (SEG) will then l evaluate the violations for acceptability. In Unit 2 the Wall Embedments and Beams (WEB) Program will track and analyze all embedded plate attachments.

We are continuing our evaluation and anticipate submitting our next report by October 20, 1986.

Very truly yours, h Su W. G. Coun'sll By: '

G.S. Keeley M Manager, Nuclear Lic(nsing JCH/amb A DIVISION OF TEXAS UTTEJTIES EZECT3tJC COMPANY

Log #.TXX-6008 File # 10110 903.7 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORT16 OLIVE EFTREET. L.B. 8 8 . DALLAS. TEXAS 75201 October 3, 1986 3.%271*,if.".it Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SEISMIC CATEGORY II SYSTEMS AND COMPONENTS SDAR: CP-86-45 (INTERIM REPORT)

Dear Mr. Johnson:

On June 6,1986, we verbally. notified your Mr. T. F. Westerman of a possible deficiency involving the interaction of non-seismic Category I structures and components with seismic Category I structures. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted interim reports logged TXX-4893 and TXX-4979 dated July 3,1986, and August 22, 1986, respectively.

The primary means at CPSES of ensuring that non-seismic Category I equipment does not affect seismic Category I equipment is to ensure that the non-seismic Category I equipment is properly mounted and anchored. This practice is common throughout the industry and was the intent of our FSAR commitment. It is also consistent with the conclusions of the NRC staff in NUREG 1030,

" Seismic Qualification of Equipment in Operating Nuclear Power Plants." We are examining our commitment and practices in detail to ensure that they are clear, precise, and provide adequate assurance of safety.

We anticipate submitting our next report by December 3, 1986.

Very truly yours,

}

W. G. Counsil l

JCH/amb c - NRC Region IV (0 + 1 copy)

, Director, Inspection & Enforcement (15 copies)

! U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEVES!ON OF TEXAS L7EI.! TIES ELECTRIC COMPANY

Leg # TXX-4979 File # 10110 903.7 TEXAS UTILITIES GENERATING COMPANT SKYW AY TOWER . 400 NORTH OLIVE STREET. L.B. A 1. DAW.AS. TEXAS TS308 August 22, 1986

.720"Aff.fl.?.S -

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SEISMIC CATEGORY II SYSTEMS AND COMPONENTS SDAR: CP-86-45 (INTERIM REPORT)

Dear Mr. Johnson:

On June 6,1986, we verbally notified your Mr. T.F. Westerman of a possible deficiency involving the interaction of non-Category I structures and components with seismic Category I structures. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). We have submitted an interim report logged TXX-4893, dated July 3, 1986.

The review of documentation related to this issue and the investigation of our projects licensing commitments and those of similar NT0L projects requires

.- additional time to complete. We are continuing our evaluation and anticipate submitting our next report by October 3, 1986.

Very truly yours, X Y W. G. Counsil By: , .

G.S. Keeley Manager, Nuclear Li nsing JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Log # TXX-6052 File # 10110 TEXAS UTILITIES GENERATING COMPANY 908.3 October-21, 1986 lE3n %??h2%t, Mr. Eric H. Johnson Division ~of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000

- Arlington, Texas 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-446 i

G0ULD BATTERY RACKS TRANSVERSE BRACING SDAR: CP-86-46 (INTERIM REPORT)

Dear Mr. Johnson:

On June 11, 1986, we verbally notified your Mr. C. Hale of a deficiency involving a design change to vendor supplied equipment being made without formal evaluation by the vendor. We have submitted interim reports logged TXX-4900 and TXX-5002, dated July 11, 1986 and September 5, 1986, respectively. We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.

DESCRIPTION l During preparation of a Unit 2 design change in 1983 involving vendor supplied equipment, conversations with the vendor (Gould) indicated the proposed change was acceptable pending evaluation of the final design change. Subsequent.

review of the design change indicates formal evaluation by TUGC0 has not been completed and was not scheduled for submittal to the vendor for formal review / approval.

The specific issue identified involves a design change revising the transverse bracing mounting bolt design from a two (2) bolt to a one (1) bolt configuration. An independent review and analysis of the one (1) bolt configuration has concluded a two (2) bolt connection is required to insure adequate strength and avoid excess eccentricity. The one bolt connection could yield under seismic loads and cause loss of the transverse bracing allowing the battery racks to become unstable. This could result in collapse of the racks. This applies to all Class IE battery racks in Units I and 2.

SAFETY IMPLICATIONS In the event the deficiency had remained undetected, the structural integrity of the battery racks could not be assured thereby affecting all. associated safety systems dependent upon DC power.

4 omsaw or rms emums nacmc co-r

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TXX-6052 October 21, 1986 Page 2 CORRECTIVE ACTION The~ design change which authorized the one (1) bolt connection has been voided and the original design requirements reestablished,'thus reverting back to the i original design of the two (2) bolt connection. l TUGC0 Nuclear Engineering Procedure TNE-DC-8-1, " Engineering Review and Design Verification of Field Design Changes," (currently Rev.10) has been revised and now provides more detailed instructions and establishes a verifiable approval record of all design changes including calculations.

Completion of the associated rework is scheduled for April 15, 1987. We anticipate submitting our next report no later than May 1, 1987.

V t ul W. G. Co sil

/

By: , -

G.S. Keeley & /_

Manager, Nucleary' Licensing JCH/gj c - Region IV (Original + 1 copy)

~

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l

l l

i

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LCg # TXX-5002 File # 10110 4' 908.3 TEXAS UTILITIES GENERATING COMPANY uv Ar vo . === ouv= ,r===r. i .. . . u.A5. T=XAS MW September 5,.1986

*2t' * .%*:i%

Mr. Eric H. Johnson, Director i Division of Reactor Safety and Projects '

U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012  !

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-446 G0ULD BATTERY RACKS TRANSVERSE BRACING SDAR: CP-86-46 (INTERIM REPORT)

Dear Mr. Johnson:

'On June 11, 1986, we verbally notified your Mr. C. Hale of a deficiency involving a design change to vendor supplied equipment being made without formal evaluation by the vendor. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have~ submitted an interim report logged TXX-4900, dated July 11, 1986.

j The specific issue involves a design change to Gould battery racks which revises the transverse bracing mounting bolt. design from a two-bolt to a one-bolt configuration. This issue is applicable to all Class 1E battery racks in

, Unit 2. Currently, the technical disposition of the nonconformance and

~

resolution of the associated design changes are.in preparation. Completion of these activities is currently scheduled for September 30, 1986.

1 We are continuing our evaluation and anticipate submitting our next report by October 21, 1986.

Very truly yours, Ndf W. G. Counsil JCH/amb c - NRC. Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies) ,

U. S. Nuclear Regulatory Commission l Washington, D.C. 20555 l A alvxsuoN OF TEXA8 UT1UTRES EE ECTERC COMFANY

-File # 10110 909.5 TEXAS UTILITIES GENERATING COMP.tNY SKYW AY TowE3 400 PsOlsTH O1JVE STREET. L.B. e n . DAhs. TEAAS 78304 July 16, 1986

."nW"L*af.??.'A Mr. Eric'H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan P1aza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK S' TEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 FIRE PROTECTION SEAL DESIGN SDAR: CP-86-47 (INTERIM REPORT)

Dear Mr. Johnson:

On June 16, 1986, we verbally notified your Mr. C. Hale of a ceficiency involving a generic design concern.with the qualification of fire barrier seals supplied by BISCO. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

We are continuing our evaluation and anticipate submitting our next report oy August 29, 1986.

Very truly yours, by (MtJb W.G. Cops 1 /a By:

G. S. Keeley k

Manager, T;

/

jticensing JCH/arh

~

c - NRC Region IV (0 + 1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEVESION OF TEXA - ,:TTES ELECTRIC COMPANY i'

I Log # TXX-4996 File # 10110 909.5 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NORTH OEJVE STREET. L.B. 8 3 . DALLAS. TEXA8 78301 September 10, 1986 332"Af?.f.".S Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects V. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 FIRE PROTECTION SEAL DESIGN SDAR: CP-86-47 (FINAL REPORT)

Dear Mr. Johnson:

On June 16, 1986, we verbally notified your Mr. C. Hale of a deficiency involving a generic design concern with the qualification of fire barrier seals supplied by BISCO. We have submitted an interim report logged TXX-4915, dated July.16, 1986. We received an extension in submitting this report from your Mr. T. Westerman until September 10, 1986.

The specific issue involves two (2) blockout fire stops which were installed in a larger-than-tested configuration, although one had been removed prior to inspection. The issue was identified during a comparison of the existing electrical blockout fire seals and test data submitted by BISCO. Engineering

'has reviewed the current design testing program and procedures submitted by.

BISCO to qualify the electrical block design. The deficiency could not have adversely affected the safe operation of the plant if it had remained undetected. Therefore we have concluded this situation is not reportable under the provisions of 10CFR50.55(e). Records supporting this determination are available for your inspectors to review at the CPSES site.

Very truly yours, W. G. Counsil ,

By: s .

G. S. Keeley -

Manager, Nuclear censing JCH/amb A DEVISION OF TEXAS UTILETTES ELECTRIC COMPANY

1 Log # TXX-5032 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER e 400 NORTH OI.JV4 STREET. I B. e1

• DALLAS. TEXA5 75301 September 19, 1986 Jn", ^1t??.f.".S Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ANCHOR BOLTS SUPPLIED BY HILTI SDAR: CP-86-51 (INTERIM REPORT)

Dear Mr. Johnson:

On July 17, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving a condition cited at another nuclear facility in which anchor bolts supplied by Hilti do not meet average ultimate tensile loads in certain sizds as published by the supplier. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4969, dated August 18, 1986.

We are continuing our evaluation and anticipate submitting our next report by November 14, 1986.

Very truly yours, h b W. G. Co s1 By: A G. S. Keele 88 M Manager, Licens n -

JCH/amb c - NRC Region IV (0 + 1 copy) l Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEVISION Of TEXAS UTil.ETTES ELECTE!C COMPANY

, ~.

Log # TXX-6053 File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY October 21, 1986 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 CABLE TRAY SPLICES / CONNECTIONS SDAR: CP-86-52 (INTERIM REPORT)

Dear Mr. Johnson:

On July 25, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving the splices / connections used for cable trays in Units 1 and 2. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-4981, dated August 22, 1986.

This issue was identified during as-built activities for the Unit 2 Cable Tray Hangers. We have established that splices / connections used for some tray types and sizes were not installed in accordance with specified splice patterns as defined by the cable tray manufacturer or approved design change documents.

Although the deviations do not appear to impair the functional capability of the trays, steps are being taken to provide a more definitive determination.

A testing program is being initiated to evaluate these conditions. Completion of this testing is estimated for mid-November,1986. Evaluation of test results and identification of corrective actions, if required, will be performed at that time.

a mmum or rms enums sucruc courer

_ - , , , - _ . - - , - , - ~ - - _ - - _

TXX-6053 October 21, 1986 Page 2 Based upon this schedule we anticipate submitting our next report by December

- 12, 1986.

Very trul yours, b

W. G. Counsil

}- ,f By: W" G.S. Keeley 7, Manager, Nuclear LicWnsing JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 I

i

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Log # TXX-4981 File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NORTlt OLJVE STREET. L.R. 5 5 . DALLAS. TEXA3 TS303 August 22, 1986

.*h?'ah *?.".i.',

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 CABLE TRAY SPLICES / CONNECTIONS SDAR: CP-86-52 (INTERIM REPORT)

Dear Mr. Johnson:

On July 25, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving the splices / connections used for cable trays. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

Splices / connections used for certain cable tray types and sizes have been observed which do not conform to the acceptable splice patterns defined by the cable tray manufacturer or approved field design change documents.

Additionally, the applicable QC inspection documents for Tray Types A and B did not require verification of splice / connector configurations and dimensions.

The evaluation and the identification of corrective actions (if required) for these conditions are currently being undertaken by Ebasco. We are continuing our evaluation and anticipate submitting.our next report by October 21, 1986.

Very truly yours, Wdnd W. G. Counsil By: . .

G.S. Keeley Manager, Nuclear icensing JCH/amb c - NRC Region IV (0 + 1 copy)

Dire: tor, Inspection & Enforcement (15 copies)

U. '.. Nuclear Regulatory Commission Wasnington, D.C. 20555 A DEV1SION OF TEXAS (fTILITIES ELECTRAC ContPANY

~~

Log # TXX-6054 File # 10110 903.10 TEXAS UTILITIES GENERATING COMPANY SEYWAY N e ese ,003TW OEJVM WrREST. I B. 81. DAELAS. TEXAS 75968 October 21, 1986

'. .'"M^1*.,*3f.".O

, Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Conraission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SEISMIC DESIGN OF CONDUIT SDAR: CP-86-53 (INTERIM REPORT)

Dear Mr. Johnson:

On July 25, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving the seismic design of conduit. We have submitted an interim report

logged TXX-4982, dated August 22, 1986. We are reporting this issue under the provisions of 10CFR50.55(e) and the required infcrmation follows.

l DESCRIPTION l During performance of the Unit 2 conduit structural analysis, a deficient

! design condition was observed involving the support of electrical conduit.

l The specific condition occurs when the conduit changes direction and

i. terminates in an airdrop and no support is provided between the change in

! ~ direction and the airdrops.

In the event a coupling is installed prior to the change in direction, the unsupported portion of the conduit may result in a torsional moment on the coupling during a seismic event. The inability of the coupling to resist the torsional moment could result in excessive motions at the free end of the conduit which would be resisted only by the cable. The cable or cable terminations have not been designed for.these loading conditions.

Analysis and evaluation of these conditions have determined that couplings on unsupported airdrops could rotate causing damage to the cables. This issue is applicable to certain Unit 1 & 2 unsupported airdrops on A and B Train conduits, and C Train conduits over 2 inches in diameter.

SAFETY IMPLICATIONS In the event the deficiency had remained undetected, this condition could have adversely affected the ability of safety-related systems to perform as required for safe operation and shutdown during a seismic event.

. A DrYEASON OF TEXA8 t/FILITIES ELECFBIC COMPANY

TXX-6054 Octcber 21, 1986 Page 2 CORRECTIVE ACTION In order to provide corrective measures, a testing program has been scheduled to evaluate the ability of' adhesives or clamps, applied to the conduit coupling after installation, to resist torsional moments.

We estimate completion of this testing by November 13, 1986. Our evaluation

~

of the results and identification of selected corrective actions will be completed by November 17, 1986.

We anticipate submitting our next report December 10, 1986.

Very truly yours, W. G. Counsil By: <h.

G.S. Keeley /

Manager, Nuclear Ci ensing JCH/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection'& Enforcement (15 copies) .

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 I

l l

Log # TXX-4982 File # 10110 903.10 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOtrER . 404 NORT10 OLIVE FrmEET. LB. 8, . D Ald.AS. TEXA5 7580, August 22, 1986

.*n"41*e??.f.".Th Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000-Arlington, TX 76012 SURJECT: COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) '

DOCKET NOS. 50-445 AND 50-446 SEISMIC DESIGN OF CONDUIT SDAR: CP-86-53 (INTERIM REPORT)

Dear Mr. Johnson:

On July 25, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving the seismic design of. conduit. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

This deficiency occurs whenever a conduit changes direction and terminates in an airdrop with no support provided between the change in direction and the airdrop and a coupling is present prior to the change. During a seismic event, the unsupported portion of the conduit places a torsional moment at the coupling. The inability of the coupling to resist the torsional moment may result in significant motions at the free end of the conduit which would be resisted by the cable. The cable has not been designed for the loads imposed '

by such motion.

EBASCO is presently evaluating a test program to test the ability of adhesives, applied -after the conduit was installed, to resist torsional l

moments. We are continuing our evaluation and anticipate submitting our next report by October 21, 1986.

Very truly yours,

[h W. G. Counsil

,6 By: A. '/M G.S. Keeley Q Manager, Nuclear Licensing JCH/amb A DEVESION OF TEXAS UTILETTES ELECTEJC COMPANY

, 3. N Log # TXX-6007 File # 10110 903.7 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER 400 NOItYH OI.JVE ETREET. L.B. 5 8 . D ALLAS. TEXAS 7530 8 October 3, 1986

.MMOAf?Ja*A Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, 'TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ORIGINAL DESIGN OF CONTROL ROOM CEILING SDAR: CP-86-54 (Interim Report)

Dear Mr. Johnson:

On August 6,1986, we verbally notified your Mr. I. Barnes of a potentially reportable item involving the design and installation of the control room ~

ceiling. We have submitted an interim report . logged TXX-5017, dated September 17, 1986. We have completed our evaluation and have concluded this issue is reportable pursuant to the provision of 10CFR50.55(e). Our evaluation is summarized in the attachment to this report. We anticipate submitting our next report no later than November 14, 1986.

Very truly yours, W. G. Counsil JCH/amb Attachment c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcements (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DIYiSION OF TEXAN l!TTLETIES ELECTRIC COAtPANY J

, .s.

TXX-6007 October 3, 1986 Page 2 DESCRIPTION Regulatory Guide 1.29 and the FSAR Section 3.78.2.8 specifies that Category II and non-seismic components should be designed in such a manner that failure will not adversely affect the functions of safety-related components or cause injury to operators.

During evaluation by the NRC Technical Review Team (TRT), the seismic design of the ceiling elements installed in the control room was investigated. The following matrix was provided to identify the ceiling elements and associated seismic designation:

(1) Heating, Ventilating and Air Conditioning - Seismic Category I (2) Safety-Related Conduits - Seismic Category I (3) Nonsafety-Related Conduits - Seismic Category II (4) Lighting Fixtures - Seismic Category II (5) Sloping Suspended Drywall Ceiling - Non-Seismic (6) Acoustical Suspended Ceiling - Non-Seismic (7) ~ Louvered Suspended Ceiling - Non-Seismic For non-seismic items other than the sloping suspended drywall ceiling, and for nonsafety-related conduits of a diameter of two inches or less, no evidence could be produced confirming that the possible effects of a failure of these items had been considered.

A separate reportable deficiency pursuant to 10CFR50.55(e), SDAR-CP-85-36, was issued on September 6.1985 to specifically address two-inch diameter and smaller non-seismic conduit.

SAFETY IMPLICATIONS In the event the condition had remained undetected, a failure of the control room ceiling elements could adversely affect safety-related systems, components, and operator actions under accident conditions.

CORRECTIVE ACTION The control room ceiling has been removed and a seismically-qualified ceiling is being installed. The construction of the new ceiling is scheduled for completion November 1, 1986.

f s

I

- _ . _ . _ - , , . , , , _ _ _ _ - , _ - _ , . , ~ _ ,

Log # TXX-5017 File # 10110 903.7 TEXAS UTILITIES GENERATING COMPAhT SKYWAY TOWER . 400 NORTM OEJVE STREET. L.B. S E . DAIJ.AS. TEXAS 78301 September 17, 1986 Ehtn:2??.?a2 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS..50-445 AND 50-446 ORIGINAL DESIGN OF CONTROL ROOM CEILING SDAR: CP-86-54 (INTERIM REPORT)

Dear Mr. Johnson:

On August 6,1986, we verbally notified your Mr. I. Barnes of a deficiency in the originat design and installation of the control room ceiling. Th~is is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). On September 5, 1986, we received an extension in submitting this report from your Mr. I. Barnes until September 17, 1986.

We are continuing our evaluation and anticipate submitting our next report by October 3,1986.

Very truly yours, kf&Y W. G. Co sil By: . ,  !

G. S. Keele Manager, Licens JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcements (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEVISION OF TEXAS UTILITTES ELEC7xlC COMPANY

Lcg # TXX-50ll File # 10110 903.7 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWE R ,400 NORTH OIJVE STREET. L.B. 8 8 . DALLAS, TEXAS 78301 Sep,tember 12, 1986

&"L^" *;??"A*A Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SEISMIC AIR GAP DESIGN ADEQUACY SDAR: CP-86-55 (INTERIM REPORT)

Dear Mr. Johnson:

On August 14, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving the seismic air gap design adequacy between the Auxiliary Building and Units 1 and 2 Containment Buildings. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e).

The specific deficiency involved recent calculations which indicate that a separation gap dimension should be greater than the existing design dimension during extreme high temperature conditions.

Our review has indicated this calculation used conservative assumptions. More recent calculations (based upon more realistic data) demonstrate the present design gap is acceptable. These calculations are presently being reviewed by third party reviewers. This review is currently scheduled for completion by October 31, 1986.

We are continuing our evaluation and anticipate submitting our next report by l

November 21, 1986.

Very truly yours, W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 Copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A DEV1 BION OF TEXAS UTTIJTTES ELECTRIC COMPANY l _ _ _ - - . - _ _ _ _ . , _ _ . - _ _ .. ,_. . _ . _

Log # TXX-5025 File # 10110 '

909.5 TEXAS UTILITIES GENERATING COMPANY September 19, 1986 JJ.*OfMS Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects-U~.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 DIESEL GENERATOR ENGINE CONNECTING ROD ASSEMBLIES SDAR: CP-86-56 (FINAL REPORT)

Dear Mr. Johnson:

On August 14, 1986 we verbally notified your Mr. I. Barnes of a potential deficiency involving the fastening of the standby diesel generator engine's connecting rod assembly. On September 12, 1986 we verbally requested and received an extension from your Mr. D. M. Hunnicutt in submitting the written report until September 19, 1986.

The connecting rods involved were identified by the Transamerica Delaval Inc.

(TDI) Diesel Generator Owners Group as a component which had significant known problems that were potentially generic. Based on the Pacific Northwest Laboratory (contracted by the NRC) and the TDI Owners Group findings, it was concluded that the connecting rod assemblies were acceptable for use at Comanche Peak provided that certain preservice and maintenance inspections i

were performed.

! The Unit 1 preservice inspections have been completed and the Unit 2 preservice inspection will be part of the Phase 1 Design Review / Quality Revalidation effort. The maintenance inspections have been identified in the CPSES Maintenance and Surveillance Program. Based on the engineering reviews noted above and the completed inspections, it was concluded that the potential deficiency identified by TDI does not exist at CPSES.

We have completed our evaluation and concluded this issue is not reportable pursuant to the provisions of 10CFR50.55(e).

j Very truly yours, N4 M W. G. Co nsil By: _

'G. S. KeeleL ~ /

Manager, Licen .

JCH/amb A DEVis#ON OF TEXAS (ITUJTTES ELECTEJC COMPANY

Leg # TXX-6028 File # 10110 t

903.8 TEXAS UTILITIES GENERATING COMPANY- '

SEYWAY N . 4st NORTH OLIVE WFRErr 8.B. St . DALLAS. TEXAS 78308

October 15, 1985

" fj^,".hN.UEL 8

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) '

DOCKET NO. 50-445 REINFORCING STEEL IN UNIT 1 REACTOR ~ CAVITY WALL SDAR: CP-86-57-(FINAL REPORT)

Dear Mr. Johnson:

On' August 29, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving the reinforcing steel in the Unit I reactor cavity wall.

Specifically, additional reinforcing steel for the wall wa specified and deleted through subsequent drawing revisions without supporting design i

calculations. We have ' submitted an interim report logged TXX-5050, dated .

September 29, 1986.

The concrete placement of the reactor cavity wall between elevations 812'-0" and 819'-0 1/2" was constructed in accordance with Revision 2 of drawing 2323-51-0572. Subsequently, Revision 3 of the drawing required additional reinforcing steel. The additional reinforcing steel was specified

(based upon engineering judgement) to minimize the possibility of cracking.

I Specific calculations justifying the adequacy of the wall, without the additional reinforcing steel shown in Revision 3, were not generated because the design was restored to conditions specified per Revision 2 of the drawing.

i Subsequently, additional calculations have been generated which demonstrate that the omission of the additional reinforcing does not impair the structural integrity of the reactor cavity wall, and the as-built reinforcement i configuration is adequate.

L 1

A Divis00N 09 TEXAE L'Til2 TELE ELECTRIC COMFANY 4

TXX-6028 ,

1 October 15, 1986 l Page 2 ,

We have concluded that in the event the condition had remained undetected, no  !

condition adverse to safety would exist. The issue is not reportable under the provisions of 10CFR50.55(e). Records supporting these conclusions are available for your inspectors to review at the CPSES project site.

i Very truly yours, W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 t

l l

I I

Log # TXX-5050 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPAhT SKYWAY TOWER = 400 NORTH OLIVE STREET. L.B. S & . DALLAS, TEXAS 78201 September 29, 1986 E.%YAN??.Y.7.%

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 REINFORCING STEEL IN UNIT 1 REACTOR CAVITY WALL SDAR: CP-86-57 (INTERIM REPORT)

Dear Mr. Johnson:

On August 29, 1986, we verbally notified your Mr. T. Westerman of a deficiency involving the reinforcing steel in the Unit I reactor cavity wall. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

During construction of the Unit I reactor cavity wall, additional reinforcing.

steel was added to a drawing and subsequently deleted without any record of design calculations being made. We are continuing our evaluation and anticipate submitting our next report by November 1, 1986.

Very truly yours, W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A DEVISION OF TEXAS t/TTIIFTES ELECntfC COMPANY

Log # TXX-5052 File 0 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SKYW AY TOWER . 400 NOE1H OLIVE WTREET. L.B. 81. DALLAS. TEXA5 78201 September 29, 1986 EM4' Mff.f.7.A Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 SUPPORT INSTALLATIONS - SPACING VIOLATIONS IN THE FUEL HANDLING BUILDING SDAR: CP-86-59 (INTERIM REPORT)

Dear Mr. Johnson:

l On August 29,1986,'we' verbally notified your. Mr.- T. Westerman of a deficiency involving support installations with concrete attachments spaced in violation of applicable Gibbs & Hill specifications. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

The.se installations have been completed and accepted by inspection upon reference to specific " Engineering Evaluation of Spacing Violations" (EESV) forms. These EESV forms were used without supporting design change documents authorizing the specific requirement deviation. We are continuing our evaluation and anticipate submitting our next report by November 26, 1986.

.Very truly yours,

/M 4 W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 I

A DnislON OF TEXA9 l.TTIIATTES E12LTEIC COMPANY

- 1

1. $' Log # TXX-6009 l File # 10110 1 903.8 TEXAS UTILITIES GENERATING COMPANY October 3, 1986 0.1ML*a?N:l.%

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite-1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 POLAR CRANE GIRDER AND GIRDER SUPPORT SHIM GAPS SDAR: CP-86-60 (INTERIM REPORT)

Dear Mr. Johnson:

On September 4,1986 we verbally notified your Mr. I. Barnes of a deficiency in~volving gaps between the polar crane girder and the girder support brackets.

This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

The allowable gap tolerance in the girder seat connection is not addressed in

. project specifications. Guidance provided by the cognizant engineering contractor' stated the " seated connection will not require shimming since the

. bearing area is at least the width of the bottom flange of the crane girder."

l Nine_ girders have been observed involving gaps which extend under the bottom 1

flange which have reduced the bearing surface to less than the 20 inch flange i width.

Preliminary-investigations have indicated that code allowable limits for bearing stress at the girder seats may be exceeded under at least one of the postulated load combinations. However, the determination of the effect upon the safe operation of the plant is being finalized. This evaluation is scheduled for completion by October 31, 1986.

In order to obtain an expeditious resolution of this issue, we have elected to i

shim the gaps and' provide full bearing surface at the girder seats rather than proceeding with the extensive analysis and performing inspections to determine the adequacy of the existing condition. A Design Change Authorization (DCA) document has been prepared to provide for the additional shimming of all polar

crane girder supports in Unit 1. The DCA is currently scheduled to be released by December 5,1986. Design requirements established as a result of this evaluation will. also be applied to the Unit 2 polar crane girder supports.

A DTV1SION OF TEXAS UTILETTES ELECTRIC COMPANY l

I

e

. ;* y

• TXX-6009 October 3, 1986 Page 2 We anticipate submitting our next report no later than December 17, 1986.

Very truly yours,

///f f/' h(/0k%%

W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l }(

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Log # TXX-6026 File # 10110 l

.903.8  :

TEXAS UTILITIES GENERATING COMPANY '

SETWAY N 4ED .003T58 OEJVB SM. LB. 33 . nae e am TEEAS TEMS October 17, 1986  !

UMO* N.02,

Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects ,

U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012  ;

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 POLAR CRANE RESTRAINTS '

SDAR:- CP-86-61 (INTERIM REPORT)

Dear Mr. Johnson:

On September 4,1986, we verbally notified your Mr. I. Barnes of a 5d'e'ficiency involving the restraints for the polar crane. This is an interim report of a._

potentially reportable item under the provisions of 10CFR50.55(e).

. We are continuing our evaluation and anticipate submitting our next report byf '

December 19, 1986.

\

Very truly yours, i

W. G. Counsil '

JCH/mlh c - NRC Region IV (0 & I copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Comission Washington, D.C. 20555 l

4 amssou or nz4s uns. mss suc7mc coasP4ur

..._,_..______,-_.-_-..-_.---__--_-----..----,~u-. - - - - - - - - -

r-Log # TXX-6010 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTH OfJVE ETEREET. L.B. 31. DALLAS. TEXA5 75301 October 3, 1986 n# h?a?." %

Mr. Eric H. Johnson, Director-Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 POLAR CRANE RESTRAINTS SDAR: CP-86-61 (INTERIM REPORT)

Dear Mr. Johnson:

On September 4,1986, we verbally notified your Mr. I. Barnes of a deficiency involving the restraints for the polar crane. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

- 1 Specifically, three rail to rail ground wires have been found broken, two

.,, shims have partially dislodged from under the rail, and two cadwelds connecting the ground wire to the rail have been broken indicating that movement occurred in the Unit 1 polar crane rail assembly. We are continuing our evaluation and anticipate submitting our next report by October 17, 1986.

Very truly yours, s

TM W. G. Counsil JCH/arrb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l

l A D8VESION (W TEXAN l!TELATLES ELECTRIC CUALPANY

~

Log # TXX-6011 File # 10110 903.8 TEXAS UTILITIES GENERATING COMPANT SKYWAY TOWER . 400 NORTBE OEJVE STREET. L.B. SI . DALLAS. TEXAS 73303 October 3, 1986

.WO?d3fa'.S Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 POLAR CRANE SUPPORT STRUCTURE SDAR: CP-86-62 (INTERIM REPORT)

Dear Mr. Johnson:

On September 4,1986, we verbally notified your Mr. I. Barnes of a deficiency involving a misinterpretation of the polar crane load cases. We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.

DESCRIPTION The load cases provided by the crane supplier (KRANCO) in the interface load drawing were not properly considered in the design of the supporting structure. As a result, the design does not consider the load case of the horizontal load acting simultaneously with the uplift of the crane. The adequacy of the polar crane support structure was considered indeterminate pending further analysis.

The cognizant engineering contractor has evaluated this issue and determined that the welds connecting the bottom flange of the girder and sole plate at the girder seat must be increased and the crane rail hold down clips must be replaced with heavier clips.

SAFETY IMPLICATION In the event that the interface loading containing the horizontal load acting simultaneously with vertical uplift load had remained undetected, it could have adversely affected safety related structures, systems and components in the containment.

CORRECTIVE ACTION Design Change Authorizations (DCAs) have been prepared for Unit I to provide for weld modifications at the girder seat and for replacing existing rail clips with stronger clips. The schedule for implementation will be established no later than December 5, 1986.

i a rnviswv o: rrxas errurrrs c1_rcrme co.uraxv I

w- - - - -

r

'TXX-6011 October 3, 1986 Page 2 We anticipate _ submitting our next report no later than December 19, 1986.

Very truly yours, f@2dL W. G. Counsil JCH/amb c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Log # TXX-6072 File # 10110 903.9

. TEXAS UTILITIES GENERATING COMPANY

, SKYWAY TOWSR e M NORT,( OLgyg STREET, B,3, 31. DARLAS, TEXAB 7MDB October 27, 1986 E'#f.iff.Unb Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE ~ PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 PRE-0PERATIONAL VIBRATIONAL TEST CRITERIA SDAR: CP-86-67 (INTERIM REPORT)

Dear Mr. Johnson:

On September 26, 1986, we verbally notified your Mr. Ian Barnes of a potential deficiency regarding the design calculations and tests used to qualify the Pre-operational Piping Vibration Program. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

A TUGCo review of the CPSES criteria document " Pre-operational Vibration Test Program", Issue 1, June,1980, indicated that the mathematical formulas used to determine stress endurance limits, allowabla deflection limits, and flexibility characteristics of certain piping systems may not have been accurate.

All vibration calculations and test results are being evaluated to verify the validity of the calculations in accordance with established TUGCo procedures.

We anticipate completing our review and verification process by December 3, 1986. Our next report will be submitted no later than December 19, 1986.

Very truly yours, W. G. Counsil l

l BSD/amb l

c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

, U. S. Nuclear Regulatory Commission l Washington, D.C. 20555 l

A DfVESFON Of TEMAS L71Lil1ES ELECTRIC CDMFANY

File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY

. SEYWAY TOWER ese NORT98 OLIVE STREET,1.3. On . DALI.AS. TEXAS 70338 October 29, 1986 j

.!.Y3".

• hff.US, Mr. Eric H. Johnson, Director

. Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Driva, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ELEVATED TEMPERATURE EFFECTS ON INSTRUMENT SUPPORTS AND TUBING SDAR: CP-86-70 (INTERIM REPORT)

Dear Mr. Johnson:

, On October 2,-1986, we verbally notified your Mr. I. Barnes of a potential j deficiency regarding elevated temperature effects on instrument supports and i

tubing. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

A design assessment review has identified a concern relating to the maximum design operating temperature of instrument supports and tubing. All tubing is currently being designed and installed using a maximum operating temperature criteria of 122 degrees F. Instrument supports and tubing could be exposed to temperatures in excess of 300 degrees F during certain accident scenarios (HELB or LOCA).

An engineering review and evaluation is currently being performed which addresses the above outlined concerns.

We will submit our next report on this issue no later than January 16, 1987.

l' Very truly yours, W. G. Counsil JDS/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 A BfYINON OF TEXAS LM EL5LTRE CUMPANY e

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.. - Log # TXX-6042 File # 10110 903.9 TEXAS UTILITIES GENERATING COMPANY SKYWAY N e 400 MORT,6 OLIVE STRENT. La. 88 . DAtlAS. TEXAS 7838 October 15, 1986 UM1".th.U'1 Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SMALL BORE PIPING AND SUPPORTS SDAR: CP-86-72 (INTERIM REPORT)

Dear Mr. Johnson:

On June 6,1986, we notified you of a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program (see TXX-4844). This issue was being tracked under SDAR CP-86-36, Pipe Supports. We are dividing this issue into two parts to segregate small bore piping and supports from large bore piping and supports. SDAR CP-86-36 will become "Large Bore Piping and Supports", and SDAR CP-86-72 is "Small Bore Piping and Supports".

The scope of SDAR CP-86-72 includes Unit I and 2 small bore (2" and under)

ASME class 2 and 3 piping and supports that are not part of large bore or class I stress problems which are covered in SDAR CP-86-36. Interim reports will include a tabulation by category of piping or support modifications as follows:

l) Prudent. Acceptance by physical modification versus analysis. Supports in this category may be technically acceptable; however, more time and expense would be involved than that required to physically modify the

support and qualify the modification.

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2) Recent NRC and Industry recommended practice. Modifications implemented to eliminate snubbers to enhance a plant maintainability, reduce in-service inspection, and minimize worker exposure (operating plant conditions).

. 3) Adjustment. Minor modifications (such as re-torquing or shimming)

! implemented to meet more rigorous installation criteria contained in the resolution of the external source technical issues.

4) Cumulative effects. Modifications that may be required due to the combined effect of multiple issues.

A DtVESCON Of TKKAS U11LITEK,5 ELECTRIC COMPANY

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TXX-6042 October 15,.1986 Page~2 of 2 The attached list shows the support modifications initiated to date. We are continuing our evaluation and anticipate submitting our next report by December 1, 1986.

Very truly yours, l'/D W. G. Counsil JCH/amb Attachment c - !iRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies)

U. S. Nuclear Regulatory ' Commission Washington, D.C. 20555 4

W TXX-6042 October 15, 1986 Page 1 of 1 ATTACHMENT SMALL BORE PIPE SUPPORT MODIFICATIONS Number of ILq11 Cateaory Modifications 1 Prudent 26 Recent Industry Practice 56 Adjustment 33 Cumulative Effects 32 2 Prudent 4 Recent Industry Practice 14 Adjustment 10 Cumulative Effects 74 4

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